AEET/NP-1,Study of the Neutron Spectra Emerging from Moderating Assemblies, R. Ramanna,1960

AEET/RE/1,The Fast Fission Factor, Average Age to Thermal,and Effective Delayed Neutron Fractions in Heterogenous Lattices, V.C. Deniz,1961

AEET/ROD/7,Canada India Reactor Operating Experience: Reactor Physics,N. Veeraraghavan,1963

AEET/ROD/8, APSARA Reactor Operating Experience Reactor Physics, N. Veeraraghavan,1963

AEET/ROD/9, Organization and Administration Aspects of Reactor Operations,V.S. Rao,1963

AEET/ROD/10, Commissioning of Nuclear Reactors, V.S. Rao, 1963

AEET/ROD/11, Reactor Physics, N. Veeraraghavan,1963

AEET/NP/7, Emission of Prompt Gamma-Rays in Thermal Neutron Fission of Uranium-235, S.S. Kapoor, 1963

AEET-ANAL-6, A, Hydrodynamic Model of Radioactivity, S. Gangadharan, 1963

AEET/HP/Th-16, Data on the Nuclear Properties of U-235 Fission Products, I.M. Ramakrishna,1964

AEET/HP/Th-17, Gamma Energy Release Rates From Fission Products at Short Times After Fission,I.M. Ramakrishna,1964

AEET/HP/Th-18, Build-Up of Nuclides in Cyclic Nuclear Operations:Mathematical Formulations,P.P. Damle,1964

AEET-210, S4B Program for Solving Multi-Group Transport Equations with Carlson's S₄ Approximation,M.G. Bhide,1965

AEET-227, Nuclear Data Measuring Facilities in India No Author,1965

AEET-229, Physics Aspects of Large Thorium-Fueled Fast Reactors, S.R. Shankar,1965

AEET-234, Review of Nuclear Data Related to Thorium FuelCycle, S.R. Shankar,1965

AEET-241, OLBUSTAP: A Burnup Program for Heavy Water Moderated Uniform Lattices,R. Gopalan,1965

BARC-279, Evaluation of Neutron Cross Sections on the Bases of Optical and Statistical Models,S.B. Garg,1967

BARC-362, Energy-Angle Correlation of Long Range Alpha Particles Emitted in Thermal Neutron Fission of U-235,D.M. Nadkarni,1968

BARC-363, Yield of K X-Rays from U-236 Fragments ,S.S. Kapoor,1968

BARC-371, Integration of the Point Reactor Kinetic Equations with a Periodic Reactivity Input by the Use of Quasi-Periodic Vector Solutions, M.S. Trasi,1968

BARC-I-36,Lectures on Nuclear Cross Sections,S.B. Garg ,1969

BARC-415,Intercomparison Calculations of Large-Fast Power Reactors,S.R. Shankar,1969

BARC-421,Analysis of Zero Power Reactor III Assembly 48 with Recent Cross-Section Data,L.M. Mahlingam,1969

BARC-431,Techniques for the Determination of Prompt Neutron Decay Constant Alpha and Beta 1p in Reactors,K. Subbarao,1969

BARC-439,Theoretical Analysis of the Physics Characteristics of the TARAPUR Core, M.R. Balakrishnan,1969

BARC/I-58,Status of the Physics of Fast Reactors,R.S.Singh, 1970

BARC/I-59,Revised Lag Tables for Array Analysis,S.K. Arora,1970

BARC-547,Studies of K X-Ray Emission in the Thermal Fission of U-235 and Spontaneous Fission of Cf-252,S.S. Kapoor,1971

BARC-550, Neutronics Studies of Two 500-MWe Pu-Th and U-233-Th Fast Breeder Systems,V.K. Shukla,1971

BARC-580,Fast Fission Ratio Measurements in Multi-Rod Clusters, A. Rose,1972

BARC-584, Mo-99 Fission Yield in the Thermal Neutron-Induced Fission of Pu-239 and U-235 ,H.C. Jain,1971

FBTR/01100/RP-12 Reactor Physics Data for a 500 MWe Pebble Bed Fast Reactor,S. Krishnan,1972

PBTR/01100/RP-56 Approximate Estimate of the Equilibrium Fuel Composition and Breeding Ratio for the Pebble Bed Fast Reactor, S. Krishnan, 1972

RRC-1 Radiation Damage in Reactor Materials, Reactor Research Centre Kalpakkam (RRCK),1973

BARC-663 Nuclear Cross-Section Calculations Using R-Matrix, M. Balakrishnan,1973

FBTR/01100/73/RP-32 Program XSAVG: A Code to Generate Multigroup Cross Sections,M.L. Sharma,1973

PBTR/01100/73/RP-50 Multigroup Cross Sections of Interest for Fast Reactors Using Latest Evaluations,M.L. Sharma,1973

BARC/I-294 Engineering Experiments for Kalpakkam Pulsed Fast Reactor: Summary Report,A. Kakodkar,1974

500FBR/01/2 Dependence of the Total Plutonium Inventory of a Large Fast Reactor on the Core Volume,S. Krishnan,1974

500FBR/01/5 Breeding Ratio Variation with Blanket Thickness for a Large Fast Reactor,T.M. John,1974

PBR500/31/74/1 Preliminary Design of Core for PBR-500,B. Singh,1974

PBTR/01140//74/RP-58 A Comparative Study of Methods to Analyze Reactor Power Behavior under Scram Conditions,O.P. Singh,1974

RRC-FRG/01100/RP-68 2DHEX - A Computer Program to Solve the Neutron Diffusion Equation in Hexagonal eometry,T.M. John,1975

RRC-FRG/01100/RP-73 PBTR Total Power and Power Per Fuel Assembly, S.M. Lee,1975

RRC-FBTR/66200/DN-06/R-0-1 Neutron Source for a Startup of FBTR, D.B. Sangodkar,1975

RRC-FRG/01100/RP-81 PERTALCI - A Two-Dimensional Diffusion Theory Perturbation Code,S. Krishnan,1975

RRC-FRG/01100/RP-82 Analysis of Typical Fast Reactor Critical Experiments, M.L. Sharma,1975

RRC-FRG/01100/RP-92 Preliminary Study of Burnup and Fuel Management in FBTR,L. Srinivasan,1975

RRC-PBR-500/01/08 A Comparison of the Breeding Ratios with Integrated and Separate Axial Blankets in FBR-500,T.M. John,1975

RRC-8 R. R. C. Activity Report up to December 1974, Reactor Research Centre, Tamilnadu ,1975

RRC-10 Shock Structures Interactions, Reactor Research Centre, Tamilnadu ,1976

RRC-19 Preliminary Physics Design of a 500 MWe Fast Breeder Reactor, T.M. John,1976

RRC-FRG/RP-105 Gamma-Ray Heating in FBTR, I. Vaidyanathan,1976

BARC-864 Core Followup Studies of the TARAPUR Reactors with the Three Dimensional BWR Simulator COMETG,S.R. Dwivedi,1976

BARC-867 Physics Operating Experience and Fuel Management of RAPS-1 ,A.N. Nakra,1976

BARC-891 Determination of Nuclear Fuel Burn-Up Using Mass Spectrometric Techniques,B. Saha,1977

RRC-16 An Analysis of the Breeding Capability of Various Fast Reactor Fuels ,C.P. Reddy,1977

RRC-19 Activity Report 1975 - Reactor Research Centre Kalpakkam, G. Ananthakrishna,1977

BARC-892, A 27 Group Cross Section Set Derived from ENDF/B Library,S.B. Garb,1976

BARC-906, Criticality Studies of Fast Assemblies with the New 27-Group Cross-Section Set ,S.B. Garg,1976

BARC-924,CREST: A Computer Program for the Calculation of Composition Dependent Self-Shielded Cross-Section,S.K. Kapil,1977

BARC-936, Statistical Model Calculations of Fission Isomer Excitation Functions in (N,N') and (N,gamma) Reactions,A. Chatterjee,1977

BARC-957, Kinetics of Zero Energy Fast Reactor PURNIMA,S. Das,1977

RRC-FRG/RP-134 Effect of Density Variation of the Thoria on the Breeding Ratio of FBTR,S. Krishnan,1977

RRC-FRG/RP-141 Initial Evolution of the Core and Blanket, Subassemblies of FBTR,C.P. Reddy,1977

NBS Spec. Pub. Inelastic Scattering of 279-keV Gamma Rays by Bound Electrons in Heavy Atoms, D.S.R. Murthy,1977

NBS Spec. Pub. Gamma Ray Attenuation Coefficient Measurements at 1115, 1173 and 1132 keV,S. Gopal,1977

NBS Spec. Pub. Compton Scattering of 1.12 MeV Gamma Rays by K-Shell Electrons,P.N. Prasad,1977

NBS Spec. Pub. Passage of Heavy Charged Particles Through Matter, S. Mukherji,1977

NBS Spec. Pub. Gamma Ray Build-Up Factors for Finite Media, K. John,1977

INIS-mf-4824 Semi-Empirical Approach for Predicting Neutron-Induced Fission Cross Sections in the Energy Range1-18 MeV, M.L. Jhingan,1978

INIS-mf-4832 PECITIS-II, A Computer Program to Predict the Performance of Collapsible Clad UO₂ Fuel Elements,A.K. Anand,1978

BARC-989 New Consistent Definition of the Homogenized Diffusion Coefficient of a Lattice, Limitations of the Homogenization Concept, and Discussion of Previously Defined Coefficients, V.C. Deniz,1978

RRC-22 Three Dimensional Multigroup Diffusion Theory Cods VANITA and TRIPHEX Based on the Method of Variational Calculus, L. Srinivasan,1978

RRC-23 Analysis of Selected Fast Critical Assemblies, M.L. Sharma,1978

RRC-25 Activities Report 1976 - Reactor Research Centre, Kalpakkam,G. Ananthakrishna,1978

BARC-1000 ENDF/B Based 27-Group Cross-Sections for some Rare Earth and Concrete Elements,S.B. Garg,1979

RRC-29 A Linear Model of the Fast Breeder Test Reactor Plant,S.S. Kumar,1979

RRC-33 Status of Noise Studies in LMFBR's and an Assessment of Their Feasibility in FBTR,O.P. Singh,1979

RRC-36,Activity Report 1977 - Reactor Research Centre, Kalpakkam, L.V. Krishnan,1979

RRC-40 Activity Report 1978 - Reactor Research Centre, Kalpakkam,L.V. Krishnan, 1979

RRC-FRG/NT/79/1 A Review and Performance Analysis for Dissociating Gas Cooled Fast Reactor,B. Singh,1979

RRC-FRG/RP-171 The Study of the Effects of Neutron Source strength on the Energy Release in a HCDA during Startup of FBTR, O.P. Singh,1979

BARC-1001 Multigroup P8 - Elastic Scattering Matrices of Main Reactor Elements,S.B. Garg,1979

BARC-1002 Multigroup Resonance Self-Shielding Factors and Cross-Sections of Main Reactor Elements,S.B. Garg,1979

BARC-1049 A Two-Dimensional Space-Time Kinetics Model using the Adiabatic Approach,H.P. Gupta, 1980

BARC-1067 Monte Carlo Validation of Supercell Model for BWR Fuel-Assembly Calculations,H.C. Gupta,1980

RRC-42 Evaluation of Statistical Resonance Parameters for Th²³³ in 4 to 41 keV Energy Region ,S. Ganesan ,1980

RRC-43 Evaluation of Resonance Parameters in Resolved and Unresolved Resonance Region for U^233,S. Ganesan,1980

BARC-1069 Supercell Burnup Model for the Physics Design of BWR Fuel Assemblies,V. Jagannathan ,1980

RRC-FRG/RP-200 Analysis of Fast Critical Assemblies in Support of Criticality Predictions for FBR-500,S. Ganesan,1980

INIS-mf-5877 Comparison of Neutron Scattering Cross Sections with the JLM Microscopic Optical Model,S. Kailas, 1980

INIS-mf-5878 Pre-Equilibrium Effects in (N,2N) Cross Sections at 14.5 MeV,S.K. Gupta,1980

INIS-mf-5879 (N,2N) and (N,3N) Cross Sections on the Basis of statistical Model for Fissionable Nuclei,M.L. Jhingan,1980

INIS-mf-5880 Monte Carlo Calculations for Intermediate-Energy Neutron Field,O.P. Joneja,1980

INIS-mf-5882 Measurement of Neutron Capture Cross Section of ²³²Th By Activation Method,H.M. Jain,1980

INIS-mf-5885 Status and Accuracy of Neutron Data for the

Important Isotopes Relevant to the Thorium-Uranium Fuel Cycle in the Fast Energy Region,M.K. Mehta,1980

PFBR/01130/2 Preliminary Neutronics Data for PBFR from One Dimensional Diffusion Calculations,T.M. John,1980

BARC-1120 Trombay Criticality Formula for the Characterization of Neutron Leakage Variations from Small Reactor Assemblies. Part I: Basis,A. Kumar,1981

BARC-1121 Trombay Criticality Formula for the Characterization of Neutron Leakage Variations from Small Reactor Assemblies. Part II:Applications,A. Kumar,1981

BARC-1129 Iterative Solutions of Finite Difference Diffusion Equations,S.V.G. Menon,1981

RRC-44 System for Analysis of Physical Progress of FBTR Project,S. Subramanian,1981

RRC-45 Activity Report 1979 & 1980 - Reactor Research Centre, Kalpakkam,L.V. Krishnan,1981

RRC-46 Sensitivity Analysis and Its Applications,V. Sundaraman,1981

RRC-48 Monte Carlo Simulation of the Benchmark Experiment in Neutron Transport in Thick Sodium,L. Murthy,1981

RRC-51 Computer Code for the Monte Carlo Simulation of Knudsen Effusion,R. Saikumur,1981

PFBR/01130/2 Control Rod Requirements of PFBR,T.M. John,1982

PFBR/01130/4 Two Dimensional Control Rod Calculations for PFBR, S.M. Lee, 1982

PFBR/01170/23 Dynamic Reactivity Coefficients and Stability Analysis of PFBR,O.P. Singh,1982

RRC-56 Activity Report of the Reactor Engineering Laboratory, 1981,R. Veerasamy,1982

RRC-57 Variational-Modal Expansion Method for Space-Time Kinetics,L. Srinivasan,1982

RRC-58 Activity Report of the Reactor Physics Section, 1982,C.P. Reddy,1983

RRC-61 Analysis of ZPR-9 Assembly 31, The Advanced Fuels Program Carbide: Benchmark Critical Assembly,S. Ganesan,1983

PFBR/01130/5 Comparison of Neutronic Parameters for Carbide and Oxide Fuels in PFBR,T.M. John,1983

BARC-1198 Guide to the Use of SUPERB Code,V. Jagannathan,1983

BARC-1222 BARC-35: A 35 Group Cross-Section Library with P₃ Anisotropic Scattering Matrices and Resonance Self-Shielding Factors,S.B. Garg,1984

RRC-64 Activity Report of Reactor Physics Section, K.P.N. Murthy, 1984

BARC-1224 Radiochemistry Division Annual Progress Report for 1982,V.K. Bhargava,1984

BARC-1228 Some Topics in Matrix Iterative Analysis, D.C. Khandekar,1984

BARC-1231 Measurement of Fast Neutron Flux Profile Across the Inner Face of the MAPP-1 End-Shield During Reactor Commissioning,H.K. Dravid,1984

BARC-1248 Fission Yields in the Thermal Neutron Fission of Plutonium-239,H.C. Jain,1984

BARC-1249 Nodal Expansion Method for Reactor Core Calculations,A. Kumar,1984

RRC-71 Radiochemistry Programme: Biennial Progress, Report, 1982-1983,N.P. Bhat,1984

REDG/RP-245 Requirements of Auxiliary Neutron Source for FBTR Start Up,K.P.N. Murthy,1984

REDG/RP-247 Neutron Data for Small Carbide Core,G.P. Reddy,1984

REDG/RP-251 Initial Evolution of the Fuel and Blanket Subassemblies of PFBR,P.T. Krishnakumar ,1984

REDG/RP-257 Maiximum Permissible Reactivity Addition Rates During Startup of PFBR - Carbide Core,M.V. Parikh,1984

REDG/RP-258 Study of Some Transients in FBTR Small Carbide Core,M.V. Parikh,1984

INIS-mf-10091 DHRUVA,No author,1984

BARC-1258 Nuclear Design Report on TARAPUR 7 x 7 Reload-3 Fuel,V. Jagannathan,1985

BARC-1261 TREDIT - A 3-D Multigroup Diffusion Theory Simulator for Hexagonal Fuel Assembly Cores,P. Mohanakrishnan,1985

BARC-1263 Low Incremental Control Worth Reload Patterns for BWR's,L.P.Burte,1985

PHWR500/PHY/3 Comparison of 500 MWe PHWR Simulations by TAQUIL and FEMINA,R. Srivenkatesan,1985

PHWR500/PHY/5 Two Group Lattice Parameters for 500 MWe PHWR, P.D. Krishnani ,1985

PHWR500/PHY/7 Evaluation of Homogenisation Errors in a Typical Lattice,S.V.G. Menon,1985

PHWR500/PHY/9 Revised Burnup Estimate for 500 MWe PHWR, K.R. Sriinivasan,1985

PHWR500/PHY/11 Burnup Optimization with Larger Inner Zone Radius for 500 MWe PHWR,A.N. Nakra,1985

PHWR500/PHY/13 Adjuster's Rods Worth for 500 MWe PHWR - Supercell Calculations,S.B. Degwekar,1985

PHWR500/PHY/14 Spatial Xenon Oscillations in Large PHWR,A. Kumar,1985

PHWR500/PHY/16 Analysis of 37-Rod Fuel Cluster in ZED-2 Reactor, P.D. Krishnani ,1985

PHWR500/PHY/17 Revised Lattice Parameters for 500 MWe PHWR, P.D. Krishnani ,1985

ThPD/HPD/655 Defueling Studies for RAPS-1, H.D.Purandare ,1985

BARC-1265 FEMSYN - A Code System to Solve Multigroup , Diffusion Theory Equations Using a Variety of Solution Techniques, Part I: Description of Code System - Input and Sample Problems,V. Jagannathan,1985

BARC-1266 FEMSYN - A Code System to Solve Multigroup, Diffusion Theory Equations Using a Variety of Solution Techniques, Part II: DIFXYZ - The Finite Difference Module, V. Jagannathan, 1985,

BARC-1267 FEMSYN - A Code System to Solve Multigroup, Diffusion Theory Equations Using a Variety of Solution Techniques, Part III: FINERC - The Finite Element Module, V. Jagannathan ,1985

BARC-1268 FEMSYN - A Code System to Solve Multigroup , Diffusion Theory Equations Using a variety of Solution Techniques, Part IV: SYNTHD - The Synthesis Module,V. Jagannathan , 1985

RRC-73 Activity Report of Reactor Physics Section 1984, O.P. Singh,1985

BARC-1295 BOXER3: A Three Dimensional Integral Transport Code for PHWR Supercell,No author, 1985

NP-5900960 Radiochemistry Program, Progress Report, 1980-1981,N.P.Bhat, 1985

BARC-1353 Neutron Radiative Capture Cross Section of ²³²Th in the Energy Range 0.1 to 1.2 MeV, H.M. Jain,1987

BARC-1367 COMESH - A Corner Mesh Finite Difference Code to Solve Multigroup Diffusion Equations in Multidimensions,V. Jagannathan,1987

BARC-1427 Importance of Biasing for 1-D Deep Penetration, H.C. Gupta,1988

BARC-1442 Reactor Physics Computer Code Development for Neutronic Design, Fuel Management, Reactor Operation and Safety Analysis of PHWR's,B.P. Rastogi,1989

BARC-1443 INDHAN: An Auto Fuel Program for PHWR's, R.P. Hhanvij,1989

BARC-1444 PHANTOM-COMESH Code System for PHWR Design, Computations,V. Jagannathan,1988

BARC-1463 HEXG - A Centre Mesh Finite Difference Code to Solve Multigroup Diffusion Equations in Two Dimensional Hexagonal Geometry,V. Jagannathan,1989

RASD/PHY/17 Evaluation of Phase-B Low Power Physics Experiments in NAPP-1, Pre-Experimental Studies,R. Srivenkatesan,1989

RASD/PHY/23 A Post-Analysis of the NAPS-1 Subcritical and Low Power Physics Experiments with PHANTOM - CEMESH Code System, V. Jagannathan,1989

BARC/I-969 Point Kinetics Code MRIF-FUEL, V.K. Jain ,1989

BARC-1493 Numerical Analysis of Antithetic Variates in Monte Carlo Radiation Transport with Geometrical Surface Splitting,P.K. Sarkar,1989

BARC-1497 New Approach to Determine Mass-Charge-Yields and Kinetic Energy Distributions in Fission, I. Datta,1990

BARC-1515 TRIHEX-3D: A Multigroup Diffusion Theory Code Hexagonal Lattice Core Analysis with Auto-Triangularisation, V. Jagannathan,1990

BARC-1525 Sensitivity Study of a Fast Breeder Reactor Dynamic Behavior Using Point Kinetics Method,S. Das,1990

BARC-1529 Analysis of a 2-D Benchmark on Interactive Effects of Gadolinium Poisoned Pins in BWR's with Monte Carlo, H.C. Gupta,1990,

BARC-1531 BARC 75 - A 75 Group Neutron-Photon Coupled Cross-Section Library with P5 Anisotropic Scattering Matrices, S.B. Garg,1990

RED/RP/FC/26 A Review of Shutdown Systems for the Standardised 235 MWe PHWR,K. Balakrishnan, 1990

RED/RP/FC/27 NARORA Criticality Calculation, K. Balakrishnan,1990

RED/RP/FC/29 Reactivity Load Calculation for Incore Neutron Noise Measurement Assembly,J.A. Nathan,1990

RED/RP/FC/30 Calculations of Errors in the Estimation of

Reactivity Worth by Stable Period Measurement,J.A. Nathan,1990

RED/FDG/2/90 Fuel Performance Evaluatin,K. Anantharaman,1990

ThPD Note/326 Follow-Up Stduies Using MOX-7 Bundles in RAPS, O.V. Lawande,1990

ThPD Note/327 Analysis of IAEA - Lattice Benchmark for Pressurized Heavy Water Reactors,H.P. Gupta,1990

ThPD Note/328 Review of Korean Experience in Fuel Performance and Burnup Extension,A.N. Nakra,1990

Interim Reports of the PHWR Fuel Performance Review Committee, 1990: R.F. Dhanvij, Methods to Improve Discharge Burnup in NAPP Type Reactors; H.D. Purandare, Burnup Optimisation Based Upon Differntial Fuelling; H.D. Purandare, Use of Reactivity Boosters in PHWR's of 235 MWe; H.D. Purandare, Irradiation of Thorium in Absorber Rod Locations in NAPP

ThPD Note/330 Burnup Extension Considerations in 1000 MWe ANDU Reactors - Canadian Experience,A.N. Nakra,1990

ThPD Note/331 Analysis of IAEA Supercell Benchmark for Pressurised Heavy Water Reactors,H.P. Gupta,1990

BARC/I-1006 Analysis of NAPS-1 First Criticality and Phase B Commissioning Physics Experiments,R. Srivenkatesan,1990

PHWR500/PHY/32 Lattice Calculations for 37 Rod Cluster of CANDU 600,T.N. Sandhya,1990

PHWR500/PHY/33 Keff as a Function of Burnup Using Revised Data of Fuel Bundle and Other Components of 500 MWe PHWR,T.N. Sandhta,1990

BARC-1543 MONALI-Rev. 1: A Monte Carlo Code for Analyzing Fuel Assemblies of Nuclear Reactors,H.C. Gupta,1991

BARC-1992/E/012 Feedback Compensation Network Design for KAPP Reactor Regulating System,B.R. Bairi,1992

BARC-1992/E/017 CLUB- A Multigroup Integral Transport Theory Code for Lattice Calculations of PHWR Cells,P.D. Krishani,1992

BARC-1994/E/013, Fuel Performance Analysis Code "FAIR", P.P. Swami, 1994

BARC-1996/E/022, Performance of Code 'FAIR' in IAEA CRP on FUMEX, P. Swami Prasad, 1995

Conference Papers:

Proc. Nucl. Phys. Solid State Phys. Symp., Bombay 1966, p300-2, D.C. Sahni, Multiple Collision Probabilities in Thin Slabs

Nuclear Physics and Solid State Physics Symposium, Powai, India, 1968, H.K. Bhatia, The Physical Feasibility of Recycling the Plutonium from Rajasthan Reactors in the Tarapur Core

Nuclear Physics and Solid State Physics Symposium, 1972, F. Ahmed, A New Variational Method for Pulsed Neutron Problem

Nuclear Physics and Solid State Physics Symposium, 1972, V.R. Nargundkar, Physics Design Aspects of a Pulsed Fast Reactor

Nuclear Physics and Solid State Physics Symposium, 1972, M. Srinivasan, Exploitation of Information Content in Second Moment of Count Rate During Approach-to-Critcal Experiments

Nuclear Physics and Solid State Physics Symposium, 1972, P.K. Ivengar, Critical Facility of the Pulsed Fast Reactor

Proc. of the International Symposium on Radiation Physics, Calcutta, India, 1974, p87-90, D.C. Sahni, Neutron Transport Problems in Spherical Geometry

Proc. of the International Symposium on Radiation Physics, Calcutta, India, 1974, p94-6, V.K. Sundaram, Criticallity Calculations by Source-Collision Iteration Technique for Cylindrical Systems

Proc. of the International Symposium on Radiation Physics, Calcutta, India, 1974, p149-62, L.S. Kothari, Neutron Thermalization in Hydrogenous Moderators

Proc. Symp. React. Phys., 1976, p41-8, S.D. Paranjape, One Group Criticality Problem of an Infinite Rectangular Parallelopiped Using the Sn Model

Proc. Symp. React. Phys., 1976, p49-53, R. Vaidyanathan, Use of a Modified Discrete Ordinates Approximation for Neutron Transport Equation in Slab Geometry

Proc. Symp. React. Phys., 1976, p62-7, P. Mohanakrishnan, Response Matrix Method for Many Neutron Energy Group Calculations - Rectangular Geometries

Proc. Symp. React. Phys., 1976, p68-71, S. Garg, Space- and Angle-Dependent Steady-State, Thermal-Neutron Spectra Inside Finite Assemblies of Coherent and Incoherent Moderators

Proc. Symp. React. Phys., 1976, p72-6, A.N. Verma, Study of Space-Dependent Steady-State Thermal-Neutron Spectra Inside Finite Blocks of Beryllium by Solving Three-Dimensional Diffusion Equation Using Synthesis Method

Proc. Symp. React. Phys., 1976, p82-5, M.M. Ramanadhan, Equiprobability Method for Monte Carlo Simulation

Proc. Symp. React. Phys., 1976, p86-90, S.K. Rao, Studies with a Time Dependent Neutron Transport Code

Proc. Symp. React. Phys., 1976, p96-9, R. Srivenkatesan, ODEON - A One Dimensional Reactor Dynamics Code for Thermal Reactors

Proc. Symp. React. Phys., 1976, p100-4, P.D. Krishnani, Solution of 3-Dimensional Diffusion Equation by Finite Fourier Transformation

Proc. Symp. React. Phys., 1976, p105-8, O.P.K. Paul, Representation of Boundary Conditions in Thermal Reactor Global Analysis by Diffusion Theory Employing Finite Difference Approximation

Proc. Symp. React. Phys., 1976, p109-12, O.P.K. Paul, An Approach to Box Homogenization - Lattice Properties

Proc. Symp. React. Phys., 1976, p113-19, A. Kumar, A Universal Empirical Relation for the Variation of k_eff with Core Dimensions of Bare and Reflected Small Fast Systems

Proc. Symp. React. Phys., 1976, p137-52, H.C. Huria, Multigroup Methods in Thermal Reactor Calculations

Proc. Symp. React. Phys., 1976, p153-5, H.C. Huria, MURLI - Multigroup Code for Thermal Reactor Lattice Calculations

Proc. Symp. React. Phys., 1976, p156-9, H.C. Huria, Analysis of Plutonium Enriched Lattices with MURLI

Proc. Symp. React. Phys., 1976, p160-3, P. Mohanakrishnan, Comparison of Experimental Measurements in Uniform Water and Deuterium Oxide Moderated Lattices with Predictions of Multigroup Collision Probability Methods

Proc. Symp. React. Phys., 1976, p164-7, V.K. Jain, Reactivity and Local Power Distribution Predictions for Tarapur Reactor Fuel Bundles

Proc. Symp. React. Phys., 1976, p168-72, S. Dwivedi, Uncertainties in Power Distribution Calculations for Enriched Uranium and Plutonium Lattices

Proc. Symp. React. Phys., 1976, p173-6, H.K. Bhatia, Analysis of Enriched Uranium Dioxide Light Water Moderated Lattices Using CAROL Code

Proc. Symp. React. Phys., 1976, p275-9, A.N. Nakra, Flux Peaking Studies in RAPS-1

Proc. Symp. React. Phys., 1976, p299-303, K. Balakrishnan, Analysis of Some Seven Rod Clusters of Metallic Uranium using the Computer Code DUMLAC

Proc. Symp. React. Phys., 1976, p308-11, K. Balakrishnan, The Computer Code BEFORE

Proc. Symp. React. Phys., 1976, p312-15, K. Balakrishnan, A Method for the Optimization of the Control Rod Configuration in a Reactor

Proc. Symp. React. Phys., 1976, p316-21, O.P.K. Paul, Some Physics Aspects of the Finalized R-5 Reactor Design

Proc. Symp. React. Phys., 1976, p355-9, S.L. Mehta, Measurement of Flux Perturbation Effects and Reaction Rates in Plutonium-Aluminum Booster Rods of ZERLINA

Proc. Symp. React. Phys., 1976, p360-3, M. Subramanian, Reactivity Worth Measurements of Plutonium-Aluminum Booster Rods and R-5 Gadolinium Liquid Poison Tubes in the ZERLINA Reactor

Proc. Symp. React. Phys., 1976, p368-70, H.M. Jain, A Program for Calculating the Thermal Flux Distribution in Computer Lattice Consisting of Clustered Elements

Proc. Symp. React. Phys., 1976, p392-5, S.M. Lee, Power Flattening by Enrichment Zoning in a Fast Power Reactor

Proc. Symp. React. Phys., 1976, p405-12, V.R. Nargundkar, Application of Pulsed Neutron Technique for Integral Neutron Cross Section Tests in the MeV Range

Proc. Symp. React. Phys., 1976, p421-3, S.S. Joshi, Auto-Power Spectral Density Measurements in ZERLINA

Proc. Symp. React. Phys., 1976, p430-3, H.K. Dravid, Measurements of Fast and Epithermal Spectra in Apsara

Proceedings of the Second Symposium on Power Plant Dynamics and Control, Hyderabad, India, 1979, A.K. Banerji, Pressurised Water Reactor Dynamics

Proceedings of the Conference, 1980 Advances in Reactor Physics and Shielding, Sun Valley, Idaho, 1980, S. Ganesan, A Critical Comparison of the Methods of Predictions in Various Laboratories for Sodium Void Reactivity Effects in Fast Critical Assemblies and Recent Results at RRC

Nuclear Data for Science and Technology, 1983, p32-5, S. Ganesan, Comparisons of Calculated Self Shielding Factors With Measured Values for Pu²³⁹, U²³⁵, Fe and Na

Nuclear Physics and Solid State Physics Symposium, 1983, S.P. Dange, Neutron Multiplicity of ²⁴⁰Pu

Ninth International Conference on Transport Theory, 1985, D.C. Sahni, Fokker-Planck Transport Equation with Reference to Spherically Symmetric Problems

4th International Conference on Emerging Nuclear Energy Systems, 1986, Madrid, Spain, p214-6, M. Srinivasan, U²³³ Fuelled Experimental Reactors in India: Purnima II and Kamini

4th International Conference on Emerging Nuclear Energy Systems, 1986, Madrid, Spain, p442-4, S.B. Garg, Criticality Aspects of Reactor Configurations Fuelled with Minor Actinides

4th International Conference on Emerging Nuclear Energy Systems, 1986, Madrid, Spain, p314-5, A. Sinha, Sensitivity Studies of the Neutron Multiplicity Spectrum in the Spallation of Pb Targets

Proceedings of the 1988 International Reactor Physics Conference, 1988, Jackson Hole, WY, R. Srivenkatesan, Simulation of Reactivity Devices in PHWR's

Emerging Nuclear Energy Systems 1989, Karlsruhe, Germany, T.K. Basu, Preliminary Studies for Uranium-233 Breeding Measurements in Thorium Oxide Assembly at the LOTUS Facility

Emerging Nuclear Energy Systems 1989, Karlsruhe, Germany, M. Srinivasan, Systematics of Critcality Properties of Actinides Nuclides and Its Bearing on Long Lived Fission Waste Problems

Emerging Nuclear Energy Systems 1989, Karlsruhe, Germany, M. Srinivasan, The Emerging Option of Fusion Bredders for the Early Exploitation of Thorium in the Indian Context

Thorium Util. Proc. Indo-Japanese Seminar, 1990, p26-6, V.R. Nargundkar, Fusion Blanket Neutronics Studies at TROMBAY

Conference on Advanced Fuel Cycles, Indian Nuclear Society, 1990, K.R. Srinivasan, Studies Pertaining to Plutonium Recycle in PHWR's

National Symposium on Radiation Protection, Bombay, 1990, H.D. Purandare, Fuel Management Strategies for PHWR with Plutonium Enrichment

Eighth National Symposium on Radiation Physics, Bombay, 1990, A.N. Nakra, Analysis of Snapshot Power Distribution in Equilibrium Core of NAPP Reactor

Eighth National Symposium on Radiation Physcis, Bombay, 1990, A.N. Nakra, Comparison of Lattice Parameters of 37-Rod Fuel Cluster for 500 MWe PHWR Using Different Lattice Codes

Eighth National Symposium on Radiation Physics, Bombay, 1990, A. Kumar, Spatial Power Control in 500 MWe PHWR

Eighth National Symposium on Radiation Physics, Bombay, 1990, V. Jagannathan, An Analysis of the Hexagonal VVER Lattice Benchmark with Gd as Burnable Absorber

Proceedings of the International Conference on Reactor Physics and Reactor Computations, Tel Aviv, Israel, C.P. Reddy, Worth of Gas Expansion Modules in FBTR

Proceedings of the International Conference on Reactor Physics and Reactor Computations, Tel Aviv, Israel, N. Sathyabama, Comparison of Diffusion and Transport Theory Analysis With Experimental Results in FBTR

Adv. Chem. Eng. Nucl. Process Ind., Bombay, 1994, S.K. Bhatia, Paramteric Studies to Establish Natural Circulation in Advanced Heavy Water Reactor

Adv. Chem. Eng. Nucl. Process Ind., Bombay, 1994, A.J. Gaikwad, Flow and Pressure Profiles for the Primary Heat Transport System of Rajasthan Atomic Power Plant for the Operation with Few Isolated Reactor Channels Near the End Shield Cracks

Adv. Chem. Eng. Nucl. Process Ind., Bombay, 1994, A.J. Gaikwad, Transient Analysis of a U-Tube Natural Circulation Steam Generator

Adv. Chem. Eng. Nucl. Process Ind., Bombay, 1994, M.P.S. Walia, Role of Pressurizer in Enhancing Pressure Control System Capability in Primary System of 500 MWe PHWR

Adv. Chem. Eng. Nucl. Process Ind., Bombay, 1994, M.L. Dhawan, Removal of Decay Heat by Specially Designed Isolation Condesnors for Advanced Heavy Water Reactors

Proceedings of the 3rd International Conference on Containment Design and Operation, Toronto, Canada, 1994, S.K. Haware, Analysis of CSNI Benchmark Test on Containment Using the Code CONTRAN

Proceedings of the Fifth International Conference on Nuclear Criticality Safety, Los Alamos, NM, 1995, C.R. Gopalakrishnan, Effect of Correlated Random Numbers on the Monte Carlo Criticality Code KENO

Papers:

Nuclear Science and Engineering, 1968, Vol. 34, p33-8, F. Ahmed, Neutron-Wave Propagation Through a Crystalline Moderator. II. Graphite

Nuclear Science and Engineering, 1968, Vol. 33, p106-18, F. Ahmed, On the Space-Energy Separability of the Fundamental Mode of the Neutron Transport Operator with Isotropic Scattering

Journal of Computational Physics, 1969, Vol. 3, p416-43, S.V. Lawande, Monte Carlo Integration of the Feynman Propagator in Imaginary Time

Nuclear Science and Engineering, 1969, Vol. 35, p302, F. Ahmed, Comments on Moores Letter "On the Physical Criteria for the Limiting Critical Frequency of Neutron Waves"

Nuclear Science and Engineering, 1969, Vol. 37, p358-67, A. Kumar, Neutron-Wave Propagation in Crystalline Moderators. IV. A Two-Group Study

Journal of Nuclear Energy, 1969, p439-41, N.K. Bansal, Neutron Wave Propagation Through Graphite

Journal of Computational Physics, 1969, Vol. 3, p451-64, S.V. Lawande, Monte Carlo Evaluation of Feynman Path Integrals in Imaginary Time and Spherical Polar Coordinates

Atomkernenergie, 1970, Vol. 16, p303-5, M.P. Navalkar, Calculation of k_eff for a Bare Pu Sphere by Collision Probability Method

Nuclear Science and Engineering, 1971, Vol. 46, p203-13, F. Ahmed, Effect of Transverse Dimensions on the Diffusion Length of Neutrons in Crystalline Moderator Assemblies

Nuclear Science and Engineering, 1971, Vol. 43, p315-18, F. Ahmed, A New Variational Method for the Pulsed-Neutron Problem

Transport Theory and Statistical Physics, 1972, Vol. 2, p197-209, F. Ahmed, A Modified Variational Method for the Pulsed-Neutron Problem

Journal of Nuclear Energy, 1972, Vol. 26, p367-78, D.C. Sahni, Integral Transport Method for Two- and Three-Dimensional Neutron Transport Problems

Proceedings of the Indian Academy of Sciences, Section A, 1972, Vol. 76, p247-62, H. Singh, Thermal Deformations of a Sphere by Radiation from a Point Source

Journal of Nuclear Energy, 1972, Vol. 26, p367-78, D.C. Sahni, The Integral Transform Method for Two and Three Dimensional Neutron Transport Problems

Journal of Nuclear Energy, 1972, Vol. 26, p409-18, S. Agarwal, Neutron Scattering From One and Two Dimensional Structures

American Journal of Physics, 1972, Vol. 40, p1264-9, L.S. Kothari, Neutron Diffusion as a Random Walk Problem

Nuclear Science and Engineering, 1973, Vol. 52, p152, L.S. Kothari, Comments on "A Pulsed Neutron Experiment with Beryllium by the Use of a Gamma-Ray Flash From an Electron Linear Accelerator"

Nuclear Science and Engineering, 1973, Vol. 27, p335-7, F. Ahmed, Effect of the Shape of the Assembly on the Decay Constant in Pulsed-Neutron Experiments

Energia Nucleare, 1973, Vol. 20, p400-5, S.V.G. Menon, Solution of the Slowing Down Equation for a Mixture of Several Nuclei

Journal Of Nuclear Energy, 1973, Vol. 27, p335-7, F. Ahmed, Neutron Wave Propagation in Finite Assemblies of Graphite

Nuclear Science and Engineering, 1973, Vol 27, p402-5, S. Saini, A New Variational Method for Pulsed-Neutron and Diffusion-Length Problems in Nonmultiplying Assemblies

Journal of Nuclear Energy, 1973, Vol. 27, p825-7, V. Bhushan, Propagation of Thermal Neutron Across an Absorption Discontinuity in Graphite

Current Science, 1974, Vol. 43, p176-7, K. Subba Rao, On the Decay of ¹²⁵Sb

Atomkernenergie, 1974, Vol. 23, p195-8, S.V.G. Menon, Analytical Evaluation of Resonance Integrals

Physics Letter A, 1975, Vol. 55A, p17-8, S.T.P.V.J. Swami, Compton Scattering of Gamma Photons by L-Shell Electrons

Nuclear Science and Engineering, 1975, Vol. 57, p63-74, G.S. Gangwani, Thermal-Neutron Transport Processes in Heavy Water in the Temperature Range of 253 to 4K

Atomkernenergie, 1975, Vol. 25, p265-70, S.V.G. Menon, Evaluation of Temperature Dependent Neutron Resonance Integrals

Canadian Journal of Physics, 1975, Vol. 53, p555-7, L. Rangaswamy, On the Calculation of the Fundamental Mode of the One Velocity Neutron Transport Generator

Journal of Physics D, 1975, Vol.8, p620-8, R.M. Bansal, Pulsed Neutron Studies in Water Poisoned with Non-1/v Absorbers

Journal of Mathematical Physics, 1975, Vol. 16, p2260-70, D.C. Sahni, Neutron Transport Problems in a Spherical Shell

Atomkernenergie, 1976, Vol. 27, p87-93, P.K. Iyengar, Parabolic Coefficient of Reactivity Measurements for the Design of a Repetitively Pulsed Fast Reactor

Atomkernenergie, 1976, Vol. 28, p169-71, S.D. Paranjape, One-Group Criticality Problem of an Infinite, Rectangular Parallelepiped Using the Sn Method

Atomkernenergie, 1976, Vol. 28, p189-94, S.V.G. Menon, Fourier Transform Method for Evaluating Resonance Interaction Effects

Nuclear Science and Engineering, 1976, Vol. 59, p261-70, L. Rangaswamy, Effect of Anisotropy in Scattering on Neutron Angular Flux Inside Slabs

Nuclear Science and Engineering, 1976, Vol. 60, p276-87, S. Garg, Space- and Angle-Dependent Steady-State Thermal-Neutron Spectra Inside Small Beryllium Assemblies

Journal of Nuclear Materials, 1976, Vol. 62, p329-32, S. Ganesan, A Note on the Cross Sections for the Two Step Reaction in Nickel

Annals of Nuclear Energy, 1976, Vol. 3, p465-69, D. Biswas, Application of Natural Coordinate System in the Finite Element Solution of Multigroup Diffusion Equation

Atomkernenergie, 1977, Vol. 29, p14-16, S. Ganesan, Evaluation of Statistical Resonance Parameters for U²³⁸ Using ADDJA Code in the Unresolved Resonance Region

Nuclear Science and Engineering, 1977, Vol. 63, p24-30, A. Kumar, Neutron Wave Propagation Across a Temperature Discontinuity

Atomic Energy, 1977, Vol. 42, p383-6, V.R. Nargundkar, Measurement of the Effects of the Reactivity of Materials in a Fast Reactor

Soviet Atomic Energy, 1977, Vol. 42, p428-32, V.R. Nargundkar, Measurements of the Effects of the Reactivity of Materials in a Fast Reactor

Nuclear Science and Engineering, 1977, Vol. 62, p502-10, S. Garg, Space- and Angle-Dependent Steady-State Thermal-Neutron Spectra Inside Finite Prisms of Graphite

Nuclear Science and Engineering, 1977, Vol. 62, p745-50, A.N. Verma, Neutron Diffusion in Finite Blocks of Beryllium

Atomkernenergie, 1977, Vol. 30, p39-44, A. Kumar, A Universal Empirical Relation for the Variation of k_eff with Core Dimensions of Bare and Reflected Small Fast Systems

Journal of Physics D, 1977, p1109-15, S. Garg, Space- and Angle-Dependent Steady-State Thermal-Neutron Spectra in Finite Water Assemblies

Nuclear Science and Engineering, 1978, Vol 67, p120-8, A. Kumar, Thermal-Neutron Wave Propagation in Finite Assemblies of Beryllium and Beryllium Oxide

Atomkernengie, 1978, Vol. 31, p146-50, S. Krishnan, Analysis of Selected Fast Critical Experiments Using Recent Delayed Neutron Yield Evaluations

Nuclear Science and Engineering, 1978, Vol. 68, p220-6, P. Mohanakrishnan, Reactivity Prediction of Uniform PuO₂/UO₂/Fuelled Lattices and Pu(NO₃)₄ Solutions in Light Water

Atomkernengie, 1978, Vol. 31, p245-8, P.K. Job, Experimental Determination of k_eff Variation of Purnima I Fast Reactor During Insertion of Core Into Reflector

Atomkernengie, 1978, Vol. 31, p249-51, A. Kumar, An Integral Version of the Los Alamos Density Exponent Formula for Critical Mass Variation

Communication European Communities, 1978, Vol. 2, p657-60, T. Basu, Experimental Studies of Neuron Multiplication from Beryllium (n,2n) Reaction in CTR Blankets

Journal of Inorganic and Nuclear Chemistry, 1978, Vol. 40, p1981-2, S.G. Marathe, Absolute Yields of ⁹⁹Mo and ¹¹¹Ag in the Reactor Neutron Induced Fission of ²³⁸U

Atomkernenergie/Kerntechnik, 1979, Vol. 34, p23-27, A. Kumar, Shape Factors of Non-Critical Fast Assemblies and Their Use in K_eff Calculations

Nuclear Science and Engineering, 1979, Vol. 70, p37-52, P.K. Iyengar, PURNIMA - A PUO₂ Fulled Zero-Energy Fast Reactor at Trombay

Nuclear Science and Engineering, 1979, Vol. 72, p160-74, A.N. Verma, Anisotropy in the Scattering of Thermal Neutrons in Crystalline Moderators-Beryllium

Atomkernenergie/Kerntechnik, 1979, Vol. 33, p199-201, R. Indira, Random Sampling of Scattering Angle in Neutron Transport

Atomkernengie/Kerntechnik, 1979, Vol. 33, p202-04, S.R. Dwivedi, Multiplication Factor Evaluation of Bare and Reflected Small Fast Assemblies Using Variational Method

Nuclear Science and Engineering, 1979, 70, p309-13, T.K. Basu, Neutron Multiplication Studies in Beryllium for Fusion Reactor Blankets

Nuclear Technology, 1979, Vol. 44, p322-25, A. Kumar, Comments on " A Simple Relationship of Maximum Delta k Due to Compaction of Unmoderated Fissile Materials" and the Use of the Trombay Criticality Formula for the Same

Nuclear Science and Engineering, 1979, Vol. 69, p367-74, R.M. Bansal, Neutron Diffusion in Water Containing 1/v and Non-1/v Absorbers

Nuclear Science and Engineering, 1980, Vol. 74, p65-6, D.C. Sahni, On the Factorized Kernel Approach for Solving Multidimensional Neutron Transport Problems

Nuclear Technology, 1980, Vol. 51, p87-96, P.K. Job, Analysis of the BeO-Reflected Uranium-233 Nitrate Solution Subcritical Multiplication Experiments Conducted at Purnima Laboratories

Nuclear Science and Technology, 1980, Vol. 76, p282-94, V. Kumar, Fundamental Mode Decay Constants for Small Two- and Three-Dimensional Pulsed Neutron Moderator Assemblies

Atomkernenergie/Kerntechnik, 1980, Vol. 36, p30-2, T.K. Basu, Details of the (n,2n) Multiplication Process of 14 MeV Neutrons in Beryllium Blankets

Nuclear technology, 1980, Vol. 49, p315-20, K. Subba Rao, BeH₂ as a Moderator in Minimum Critical Mass Systems

Annals of Nuclear Energy, 1980, Vol. 7, p389-95, P. K.N. Murthy, A Comparative Study of Different Tracklength Biassing Schemes

Annals of Nuclear Energy, 1980, Vol. 7, p635-40, L.S. Kothari, One-Group Theory of a Control Rod with an Elliptical Cross Section Placed Confocally in a Multiplying System with a Similar Cross Section

Annals of Nuclear Energy, 1980, Vol. 7, p641-54, V. Jagannathan, A Fast and Reliable Calculation Model for BWR Fuel Assembly Burnup Analyses

Journal of Physics D, 1981, Vol. 14, p135-44, R. Mohan, The Existence of Equilibrium Spectra in Fast Uranium Assemblies. The Effect of Anistropy in Scattering

Annals of Nuclear Energy, 1981, Vol. 8, p173-82, V. Kumar, Integral Transform Method for Solving Multi-Dimensional Neutron Transport Problems with Linearly Anisotropic Scattering

Atomkernenergie/Kerntechnik, 1981, Vol. 37, p299-300, J.K. Ghosh, Homogeneity Evaluation in Aluminum-Plutonium Plate-Type Fuel Elements using an Americium-241 Source

Annals of Nuclear Energy, 1981, Vol. 8, p299-303, K.H.N. Murthy, Optical-Method Description of 14 MeV Neutron Cross Sections

Indian Journal of Pure and Applied Physics 1981, Vol. 19, p874-80, L.S. Kothari, Influence of Lattice Structure on the Transport of Thermal Neutrons in Beryllium

Atomkernenergie/Kerntechnik, 1981, Vol. 38, p282-4, A. Sinha, A Statistical Pre-Equilibrium Model-Based Analysis of (n,2n) and (n,3n) Cross Sections of Th²³² and U³²⁸

Nuclear Science and Engineering, 1982, Vol.81, p66-74, A. Kumar, A Modified Wigner Rational Approximation for Neutron Collision Escape Probability from Bare Homogeneous Reactor Assemblies

Indian Journal of Pure and Applied Physics, 1982, Vol. 20, p81-2, A. Viswanatha Sarma, Ultrasonic Attenuation in Some Critical Systems

Annals of Nuclear Energy, 1982, Vol. 9, p209-13, P.K. Job, Evaluation of Reactivity Bonus Due to (n,2n) Multiplication in Be/BeO-Reflected U²³³ Uranyl Nitrate Solution Systems

Nuclear Science and Engineering, 1982, Vol. 80, p218-29, A. Sadwani, Neutron Wave Propagation Across a Temperature Discontinuity-Multigroup Approach

Nuclear Science and Engineering, 1982, Vol. 81, p137-43, U. Malik, Neutron Diffusion in Graphite Poisoned with 1/v and Non-1/v Absorbers

Nuclear Science and Engineering, 1982, Vol. 82, p96-108, U. Malik, Decay of Neutron Pulses in Graphite Assemblies

Annals of Nuclear Energy, 1982, Vol. 9, p359-68, S.R. Dwivedi, A New Importance Biasing Scheme for Deep-Penetration Monte Carlo

Annals of Nuclear Energy, 1982, Vol. 9, p481-7, S. Ganesan, On the Need for Changing the ENDF/B Convection for the Representation of Cross-Sections in the Unresolved Resonance Region of Fertile and Fissile Nuclei

Nuclear Science and Engineering, 1982, Vol. 82, p307-15, K.N. Srivastava, Minimum Critical Mass Nuclear Reactors, Part I

Nuclear Science and Engineering, 1982, Vol. 82, p316-24, K.N. Srivastava, Minimum Critical Mass Nuclear Reactors, Part II

Nuclear Science and Engineering, 1982, Vol. 82, p354-64, A. Kumar, Bubble Worth Variation in Molten Fuel Assemblies Due to Neutron Streaming and Application of Trombay Criticality Formula

Nuclear Science and Engineering, 1982, Vol. 82, p359-64, S.V.G. Menon, Fourier Transform Method for a Resonance Absorption Problem in a Lattice Cell

Journal of Physics D, 1982, Vol. 15, p411-19, R. Mohan, Steady-State Fast Neutron Spectra in Slabs of Natural Uranium - A Comparison of Diffusion and Transport Theories

Nuclear Science and Engineering, 1982, Vol. 81, p532-9, R. Mohan, Decay of Fast Neutron Pulses in Uranium Assemblies

Nuclear Science and Engineering, 1983, Vol. 83, p155-64, A. Kumar, Characterization of Neutron Leakage Probability k_eff and Critical Core Surface Mass Density of Small Reactor Assemblies Through the Trombay Criticality Formula

Journal of Fusion Energy, 1983, Vol. 3, p185-97, A. Kumar, Investigations of Neutronics of some (D,T)-Driven Experimental Thorium Hybrid Blankets with Actinide Multipliers

Atomkernengie/Kerntechnik, 1983, Vol. 43, p259-61, G. Dharmadurai, Sensitivity Analysis of the Critical Constants of Fast Reactor Fuels

Nuclear Science and Engineering, 1983, Vol. 84, p293-8, P.K. Job, Additional Remarks on BeH₂ as a Moderator in Minimum Critcal mass Systems

Transport Theory and Statistical Physics, 1983-84, Vol. 12, p341-68, E.B. Dahl, Complex Time Eigenvalues of the One Speed Neutron Transport Equation for a Homogenous Sphere

Annals of Nuclear Energy, 1983, Vol. 10, p351-7, D.C. Sahni, Evaluation of the Linear Extrapolation Distance for Strong Neutron Absorbers by the Sn Method

Annals of Nuclear Energy, 1983, Vol.10, p375-8, K.N.P. Murthy, Optimal Choice of Parameters for Track-Length Biassing in Monte-Carlo Deep-Penetration Problems

Annals of Nuclear Energy, 1983, Vol. 10, p571-5, S.B. Degweker, Multiplicity Spectrum of Leakage Neutrons From Fissionable Materials

Annals of Nuclear Energy, 1983, Vol. 10, p649-63, V. Kumar, The Integral-Transform Method for Solving Neutron Transport Problems with General Anisotropic Scattering in a Cylinder of Finite Height

Journal of Physics D, 1983, Vol. 16, p715-22, P. Mohan, Thermal Neutron Extrapolation Distances for Slabs of Beryllium and Water

Journal of Chemical Physics 1983, Vol. 79, p2302-7, Y.S. Mayya, One-Dimensional Brownian Motion Near an Absorbing Boundary: Solution to the Steady State Fokker-Planck Equation

Atomkernengie/Kerntechnik, 1984, Vol. 45, p55-8, M. Srinivasan, Neutronics of Micro-Fission Systems and Application of Trombay Criticality Formula (TCF). Part I: Infinite Containment Analysis

Pramana, 1984, Vol. 22, p71-7, K.V. Subba Rao, Nuclear Compressibility and Its Effects on Nuclear Energy Binding Energies From the Study of Muonic Atoms

Indian Journal of Physics, Part A, 1984, Vol. 58A, p92, F. Ahmed, Approach to Equilibrium or Pseudo-Equilibrium of Fast Neutron Fields in Multiplying or Non-Multiplying Systems

Fusion Technology 1984, Vol. 6, p93-6, V.R. Nargundkar, Neutron Multiplication Measurement in BeO for 14-MeV Neutrons

Nuclear Science and Engineering, 1984, Vol. 86, p219-38, F. Ahmed, Calculations of the Spectra of Fast Neutrons in Iron Spheres Using the Vitamin-C File

Pramana, 1984, Vol. 22, p283-92, P. Batheja, Study of Pulsed Fast Neutrons in an Infinite Iron Assembly

Indian Journal of Physics, Part A, 1984, Vol. 58A, p469-73, M.M. Ramanadham, Generation of New Multigroup Cross Section Sets for C¹², O¹⁶, Pu²³⁹, U²³⁸ and Pu²⁴⁰ Based on ENDF/B-IV File for Fast Reactor Applications

Journal of Mathematical Physics, 1984, Vol. 25, p810-11, G.S. Singh, On the Solution of the Two-Dimensional Helmholtz Equation

Journal of Physics D, 1984, Vol. 17, p863-9, A.N. Verma, A Space and Angle Dependent Study of Neutron Wave Propagation in Beryllium

Physical Review A, 1984, Vol. 30, p2056-61, D.C. Sahni, Burnett-Function Solution of the Steady-State Fokker-Planck Equation Near an Absorbing Sphere

Nuclear Science and Engineering, 1985, Vol 90, p111-16, R. Mohan, Effect of U²³⁵ Concentrations of Fast Neutron Space and Time Eigenvalues and Eigenfunctions in Uranium

Pramana, 1985, Vol. 24, p165-77, B.P. Rastogi, Development of Thermal Reactor Lattice Physics Methods

Pramana, 1985, Vol. 24, p259-78, P.K. Iyengar, Perspectives in Neutron Physics Research

Transport Theory and Statistical Physics, 1985, Vol. 14, p353-72, S.V.G. Menon, Convergence of Discrete Ordinates Iteration Scheme

Nuclear Science and Engineering, 1985, Vol. 89, p366, P. Batheja, A Time-Dependent Study of Fast Neutrons in Iron

Transport Theory and Statistical Physics, 1985, Vol. 14, p373-82, V.C. Boffi, Critical Problems for Finite Slabs with Sinusoidally Space-Dependent Scattering Ratio

Physica A, 1986, Vol. 135A, p63-79, S.V.G. Menon, Green's Function Approach to the Solution of the Time Dependent Fokker-Planck Equation with an Absorbing Boundary

Nuclear Science and Engineering, 1986, Vol. 94, p87-93, P. Mohan, An Eigenvalue and Eigenfunction Study of Space-Dependent Fast Neutron Spectra in Th²³²

Pramana, 1986, Vol. 27, p129-37, R. Ramanna, The Thorium Cycle for Fast Breeder Reactors

Radiation Effects, 1986, Vol. 96, p259-64, S.B. Garg, Generation of ENDF/B-IV Based 35 Group Neutron Cross-Section Library and its Application in Criticallity Studies

Radiation Effects, 1986, Vol. 96, p313-16, S. Ganesan, A Programme of Evaluation, Processing and Testing of Nuclear Data for Th-²³² and U-²³³

Annals of Nuclear Energy, 1986, Vol. 13, pp539-43, R.S. Modak, Convergence of the Iteration in the Nodal Expansion Method for the Solution of the Diffusion Equation

Annals of Nuclear Energy, 1986, Vol. 13, p575-8, T.K. Basu, Experimental Study of Neutron Multiplication in BeO by the Shift-Register Coincidence Technique

Nuclear Science and Engineering, 1986, Vol. 92, p606-7, R.S. Modak, On the Discrete Ordinates Method in Spherical Geometry

Nuclear Science and Engineering, 1986, Vol. 92, p608-10, R.S. Keshavamurthy, Limitations on the Use of the THOR Critical Assembly for Validation of n+/Pu²³⁹ Cross Sections

Fusion Technology, 1986, Vol. 10, p931-9, A. Kumar, Experimental Program at the LOTUS Facility

Nuclear Science and Engineering, 1986, Vol. 94, p323-36, R. Indira, Variance Reduction Under Exponential and Scattering Angle Biasing: An Analytic Approach

Fusion Technology, 1987, Vol. 12, p114-18, O.P. Joneja, 14-MeV Neutron Multiplication Measurement in Lead

Annuals of Nuclear Energy, 1987, Vol. 14, p321-23, A.K. Jena, Study of Neutron Noise Tramsmission Characteristics in Finite Nonmultiplying Media

Nuclear Science and Engineering, 1987, Vol. 96, p330-42, K.V. Subbaiah, Effect of Fluorescence in Deep Penetration of Gamma Rays

Fusion Technology, 1987, Vol. 12, p380-94, V.R. Nargundkar, Reanalysis of Neutron Multiplication Measurements in Thick Beryllium and Graphite Assemblies for 14-MeV Neutrons

Atomkernengie/Kerntechnik, 1987, Vol. 49, p204-7, J. Jordanova, Neutron Leakage Spectra from Lead Slabs Bombarded with 14-MeV Neutrons

Transport Theory and Statistical Physics, 1987, Vol. 16, p959-78, D.C. Sahni, Numerical Solution of Singular Integral Equations of Neutron Transport Problems

Journal of Nuclear Science and Engineering, 1987, Vol. 24, p1066-69, C.R. Gopalakrishnan, Effect of Geometrical Approximation on Multiplication Factor in Small Fast Reactor Core

Annals of Nuclear Energy, 1988, Vol. 15, p67-74, R. Indira, Study of Biased Monte-Carlo Schemes Employing Weight-Moments Equation Formulation

Annals of Nuclear Energy, 1988, Vol. 15, p113-40, S. Ganesan, Verification of the Accuracy of Doppler Broadened, Self-Shielded Multigroup Cross Sections for Fast Power Reactor Applications

Fusion Technology, 1988, Vol. 13, p153-6, V.R. Nargundkar, A Comparative Study of Thermal Neutron Fusion Blanket Arrangements

Annals of Nuclear Energy, 1988, Vol. 15, p261-9, R. Indira, Analytical Study of Leakage Estimators in Monte-Carlo Simulation of Radiation Transport

Annals of Nuclear Energy, 1988, Vol. 15, p317-22, V. Kumar, Discrete Ordinates Scheme for Quadrilateral Meshes

Fusion Technology, 1988, Vol. 14, p354-9, V.R. Nargundkar, Measurement of 14-MeV Neutron Multiplication in Thorium Oxide

Physics Letters A, 1988, Vol. 133, p438-40, V.S. Bhasin, Atomic Scattering Factor for an Anisotropic Charge Distribution

Separation Science and Technology, 1988, D. Karunasagar, Rapid Determination of Burn-Up of Nuclear Fuel - A Possible Approach

Physica B, 1989, Vol. 156, p534-6, Y.D. Dande, Neutron Instrumentation for DHRUVA Utilization

Material Science Forum, 1989, Vol. 48, p109-24, M. Das, Design Aspects of PHWR for Improved Performance

Material Science Forum, 1989, Vol. 48, p109-24, M. Das, Design Aspects of PHWR for Improved Performance

Nuclear Science and Engineering, 1989, Vol. 102, p295-309, M. Srinivasan, Systematics of Criticality Data of Special Actinide Nuclides Deduced Through the Trombay Criticality Formula

Computer Physics, 1989, Vol. 55, p311-23, P. Mohanakrishnan, Use of Albedo for Neutron Reflector Regions in Reactor Core 3-D Simulations

Journal of Mathematical Physics, 1989, Vol. 30, p1554-9, D.C. Sahni, Equivalence of Generic Equation Method and Phenomenological Model for Linear Transport Problems in a Two-State Random Scattering Medium

Annals of Nuclear Energy, 1989, Vol. 16, p397-408, D.C. Sahni, An Application of Reactor Noise Techniques to Neutron Transport Problems in a Random Medium

Annals of Nuclear Energy, 1989, Vol. 16, p571-6, R. Indira, Optimization of Biasing Parameters in Particle Transport Simulations

Physica A, 1990, Vol. 165, p157-69, V. Kumar, Probability Density of the Reflection Coefficient of a Semi-Infinite Array of Random Slabs

Fusion Technology, 1990, Vol. 18, p310-16, O.P. Joneja, Neutronic Performance of Candidate Neutron Multipliers Beryllium and Lead in a Stainless Steel First Wall

Annals of Nuclear Energy, 1990, Vol. 17, p435-53, E.B. Dahl, Nature of Complex Time Eigenvalues of the One-Speed Transport Equation in a Homogenous Sphere

Progress in Nuclear Energy, 1990, Vol. 23, p421-89, D.C. Sahni, Criticality and Time Eigenvalues in One-Speed Neutron Transport

Journal of Nuclear Science and Technology, 1990, Vol. 27, p547-53, B. Prahlad, Thermal Performance Tests on a Sodium-to-Sodium Heat Exchanger

Annuals of Nuclear Energy, 1991, Vol. 18, p25-30, B. Mahalakshmi, New Formalae for Estimation of Control Rod Worths in Fast Reactors

Annals of Nuclear Energy, 1991, Vol. 18, p81-6, S. Rajagopalan, Parallel Iterative Algorithms for Solving Fundamental Mode Neutron Flux Distribution

Nuclear Engineering International, 1991, Vol. 36, p50-1, M.R. Balakrishnan, Looking at Fast Breeder Fuel with India's KAMINI Reactor

Nuclear Engineering and Design, 1991, Vol. 125, p259-66, R.I.K. Moorthy, Diagnosis and Cure for Dhruva Fuel Vibration

Nuclear Science and Engineering, 1991, Vol. 109, p373-9, K.V. Subbaiah, Mitigation of Singularity Problems in Gamma-Ray Transport in Spherical Systems

Nuclear Technology, 1991, Vol. 94, p416-20, M.R. Balakrishnan, Improvement in Fuel Utilization in Pressurized Heavy Water Reactors Due to Increased Heavy Water Purity

Journal of Nondestructive Testing, 1991, Vol. 33, p437-40, M.T. Shyamsunder, Development of Eddy Current Test Techniques for Condition Monitoring of Pressure Tube/Calandria Tube Assemblies of Indian Pressurized Heavy Water Reactors

Annals of Nuclear Energy, 1991,Vol. 18, p443-53, D.C. Sahni, Time Eigenvalues of the One-Speed Neutron Transport Equation for Spherically Asymmetric Modes in a Homogenous Sphere

Transport Theory and Statistical Physics, 1991, Vol. 20, p339-49, D.C. Sahni, Non-Monotonic Variation of the Criticality Factor with the Degree of Anisotropy in One-Speed Neutron Transport

Journal of Physics D, 1992, Vol. 25, p1381-9, D.C. Sahni, Criticality and Time Eigenvalues for One-Speed Neutrons in a Slab With Forward and Back Scattering

International Power Generation, 1992, Vol. 15, p62-5, No Author, Nuclear Update (CANDU Reactor Pressure Tube Replacement)

Annuals of Nuclear Energy, 1992, Vol. 19, p473-6, M. Srinivasan, A TCF Approach to the Criticality Aspects of Fissile Solution Systems

Journal of Computational Physics, 1993, Vol. 104, p267-72, M.R. Khorrami, Efficient Computation of Spatial Eigenvalues for Hydrodynamic Stability Analysis

Annuals of Nuclear Energy, 1993, Vol. 20, p315-9, O.P. Singh, Response of Small Reactivity Perturbations in an Oxide and Metal Fuelled Medium-Sized Liquid-Metal Fast Breeder Reactor

Nuclear Science and Engineering, 1993, Vol. 115, p341-7, B. Mahalakshmi, Analysis of Radially Heterogenous ZPPR-13A Benchmark for Investigating the Spatial Dependence of the Calculated-to-Experimental Ratio for Control Rod Worths

Annuals of Nuclear Energy, 1993, Vol. 20, p391-405, K. Balakrishnan, Reactivity Worth of Liquid Poison Jets in the Moderator

Fusion Technology, 1993, Vol. 23, p408-18, O.P. Joneja, Haefely Neutron Generator Characteristics From Neutronic Considerations and Comparison With Calculations

Fusion Technology, 1993, Vol. 23, p419-25, V.R. Nargundkar, U²³³ Production in a Thoria-and-Water Multilayered Assembly Using a 14-MeV Neutron Source

Nuclear Science and Engineering, 1993, Vol. 115, p341-7, B. Mahalakshmi, Analysis of Radially Heterogenous ZPPR-13A Benchmark for Investigating the Spatial Dependence of the Calculated-to-Experimental Ratio for Control Rod Worths

Fusion Technology 1993, Vol. 23, p419-25, V.R. Nargundkar, U²³³ Production in a Thoria-and-Water Multilayered Assembly using a 14-MeV Neutron Source

Annals of Nuclear Energy, 1993, Vol. 20, p449-53, A. Sharma, Evaluation of Fundamental Decay Constants by the Sn Method

Journal of Physics D, 1993, Vol. 26, p2101,-6, S.D. Paranjape, Asymmetric Modes and Complex Time Eigenvalues of the One-Speed Neutron Transport Equation in a Homogenous Sphere

Annals of Nuclear Energy, 1994, Vol. 21, p1-9, K. Balakrishnan, Optimization of the Initial Fuel Loading of the Indian PHWR With Thorium Bundles for Achieving Full Power

Annals of Nuclear Energy, 1994, Vol. 21, p55-59, S.B. Degweker, The Anomalous Flux Profile Observed in KAPP-1 During Its First Approach to Criticality

Annals of Nuclear Energy, 1994, Vol. 21, p195-99, R.S. Modak, A Scheme for the Evaluation of Gamma-Modes of a Neutron Diffusion Equation

Progress in Nuclear Energy, 1994, Vol. 28, p209-64, S. Das, The Importance of Delayed Neutrons in Nuclear Research - A Review

Annals of Nuclear Energy, 1994, Vol. 21, p229-33, P.T. Krishna, Estimation of Uncertainties in Absolute Neutron Cross-Section Measurement

Annals of Nuclear Energy, 1994, Vol. 21, p259-62, R. Indira, Optimization of Neutron Collars for Pu-Assay - Design Capabilities and Adequacy of Nuclear Data

Annals of Nuclear Energy, 1994, Vol. 21, p267-76, A. Sharma, Nonmonotonic Behavior of the 'C' Eigenvalue of the One-Speed Neutron Transport Equation in One-Dimensional Spherical Shells

Indian Journal of Power and River Valley Development, 1994, Vol. 44, p317-23, A. Kakodkar, Current Developments and Future Strategies for Nuclear Power Development

Transport Theory and Statistical Physics, 1994, Vol 23, p893-906, A.K. Kulkarni, Nonmonotonic Behavior of the 'C' Eigenvalue of the One-Speed Neutron Transport Problem in Two-Dimensional Cylindrical (r,z) Geometry

Physical Review C, 1994, Vol. 49, p932-40, A. Saxena, Entrance Channel Effects in the Fission-Fusion Time Scales from Studies of Precision Neutron Multiplcities

Indian Journal of Power and River Valley Development, 1995, Vol. 45, p29-35, A.K. Singh, Maintanence Experience on Reactor Recirculation Pumps at Tarapur Atomic Power Station

Annals of Nuclear, 1995, Vol. 22, p61-66, N. Sathyabama, Estimate of Total Control Rod Worth Based on Lower Dimensional Modeling

Nuclear Engineering and Design, 1995, Vol. 158, p61-80, S.B. Bhoje, Operating Temperatures for an FBR

IEEE Transactions on Nuclear Science, 1995, Vol. 42, p110-14, L. Pathak, Profiling a Reactor Component Using Ultrasoncis

Journal of Nuclear Materials, 1995, Vol. 218, p231-5, G.A. Rama Rao, Measurement of Void Volume of a Fuel Rod and the Exchange of Occluded Gases From Mixed Carbide Fuel With Filling Gas Helium

Nuclear technology, 1995, Vol. 112, p295-8, G. Dharmadurai, Transient Gap Conductance in Nuclear Fuel Rods

Nuclear Engineering and Design, 1995, Vol. 155, p571-89, R.I.K. Moorthy, Diangostics of Direct CT-PT Contact of the Coolant Channels of PHWRs

Annuals of Nuclear Energy, 1995, Vol. 22, p629-47, K. Singh, Reconstruction of Pin Power in Fuel Assemblies From Nodal Calculations in Hexagonal Geometry

Energy Conversion and Management, 1995, Vol. 36, p975-87, P. Satyamurthy, A Conceptual Scheme for Electrical Power Generation From Nuclear Waste Heat Using Liquid Metal Magnetohydrodymanic Energy Convertor

Mathematical and Computer Modelling, 1995, Vol. 22, p77-87, A.K. Nayak, Mathematical Modelling of the Stability Characeristics of a Natural Circulation Loop

Physical Review C, 1995, Vol. 51, p3127-35, M.S. Samant, Prescission Neutron Emission in ²³⁵Un/_th/f Through Fragment-Neutron Angular Correlation Studies

Fuzzy Set and Systems, 1996, Vol. 83, p135-41, P.V. Suresh, Uncertainty in Fault Tree Analysis: A Fuzzy Approach

Progress in Nuclear Energy, 1996, Vol. 30, p305-20, D.C. Sahni, Some New results Pertaining to Criticality and Time Eigenvalues of One-Speed Neutron Transport Equation

Nuclear Science and Engineering, 1996, Vol. 122, p 344-58, S. Das, A Point-Kinetics Appraoch to Sensitivity Study of Fast Reactor Dynamic Behavior and Delayed Neutron Spectra

Nuclear Science and Engineering, 1996, Vol. 122, p359-65, P. Mohnakrishnan, Estimation of Measured Control Rod Worths in Fast Breeder Test Reactor - Effect of Different Delayed Neutron Parameters

Annals of Nuclear Energy, 1996, Vol. 23, p791-800, K. Devan , Generation and Validation of a New 121 Group Coupled (n, gamma) Cross Section Library for Fast Reactor Applications

IEEE Transactions on Nuclear Power, 1996, Vol. 43, p2440-53, A.P. Tiwari, Spatial Control of a Large Pressurized Heavy Water Reactor

Review of Scientific Instruments, 1996, Vol. 67, p2197-201, K.R. Prasad, Uranium-233 Fission Detectors for Neutron Flux Measurements in Reactors

International Journal of Pressure Vessels and Piping, 1997, Vol. 73, p39-44, M. Palaniappan, Mass Spectrometer Helium Leak Testing of Large Volume Piplines and Pressure Vessels of a Nuclear Power Plant

International Journal of Pressure Vessels and Piping, 1997, Vol. 73, p59-68, P. Rodriquez, Development of In-Service Inspection Techniques for Nuclear Power Plants in India

International Journal fo Pressure Vessels and Piping, 1997, Vol. 73, p77-87, K. Shanmugan, Quality Assessment on FBTR Reactor Vessel

Nuclear Physics A, 1997, Vol. A612, p143-62, H. Naik, Systematics of Charge Distribution Studies in Low-Energy Fission of Actinides

Indian Journal of Power and River Valley Development, 1997, Vol. 47, p159-63, Y.S.R. Prasad, Indian Nuclear Power Program-Challenges and Opportunities

Transactions of the American Nuclear Society, 1997, Vol. 77, p200-2, P.D. Krishani, Method of Calculating the Effect of Heterogenous Fuel Composition on a Fuel Bundle Ramp

Nuclear Technology, 1997, Vol. 117, p299-305, M.P. Anthony, Studies on the Restructuring of Fast Breeder Test Reactor Fuel by Out-of-Pile Simulation

Fusion Technology, 1997, Vol. 31, p370-7, R. Prashad Anand , ²³³U Breeding Measurements in a Thorium-Oxide Blanket Assembly Using a (d,t) Accelerator Neutron Source

Annuals of Nuclear Energy, 1997, Vol. 24, p575-86, G. Prabhakar Rao, A Modified Code System for Transport of Accelerator Produced Neutrons Through Ordinary Concrete

Reliability and System Safety, 1998, Vol. 60, p53-69, P. V. Varde, An Operator Support System for Research Reactor Operations and Fault Diagnosis Through a Connectionist Framework and PSA Based Knowledge Based Systems

Transactions of the ASME. Journal of Pressure Vessel Technology, 1998, Vol. 120, p93-8, G.R. Reddy, Decoupling Criteria for Multi-Connected Equipment

IEEE Transactions on Nuclear Science, 1998, Vol. 45, p129-40, R.N. Banavar, Robust Controller Design for a Nuclear Power Plant Using H _infinity Optimization

Nuclear Engineering and Design, 1998, Vol. 180, p147-54, R.I.K. Moorthy, Dynamic Qualification of Complex Structural Components of Nuclear Power Plants

Annuals of Nuclear Energy, 1998, Vol. 25, p161-79, K. Devan, Preparation of Multigroup Lumped Fission Product Cross-Sections in ENDF/B-VI for FBRs

Transactions of the ASME. Journal of Fluid Engineering, 1998, Vol. 120, p207-9, H.G. Lele, Flow Regime Identification in Horizontal Channels With Different Types of Rod Clusters

International Journal of Pressure Vessels and Piping, 1998, Vol. 75, p297-306, D.S. Chawla, Assessment of Operability and Structural Integrity of a Vertical Pump for Extreme Loads

Nuclear Engineering and Design, 1998, Vol. 183, p303-9, A. Mukherjee, Artificial Neural Networks in CT-PT Contact Detection in a PHWR

Annuals of Nuclear Energy, 1998, Vol. 25, p567-79, B.P. Dubey, Quick and Relaible Estimation of Power Distribution in a PHWR by ANN

Annuals of Nuclear Energy, 1998, Vol. 25, p629-36, B.P. Dubey, Quick and Relaible Estimation of Power Distribution in a PHWR by ANN

Energy, 1998, Vol. 23, p629-36, P. Rodriquez, The FBR program in India

Journal of Nuclear Science and Engineering, 1998, Vol. 35, p712-22, A.K. Nayak, Adequacy of Power-to-Volume Scaling Philosophy to Simulate Natural Circulation in Integral Test Facilities

Journal of Nuclear Science and Technology, 1998, Vol. 35, p768-78, A.K. Nayak, Linear Analysis of Thermo-Hydraulic Instabilities of the Advanced Heavy Water Reactor (AHWR)

Annauls of Nuclear Energy, 1998, Vol. 25, p839-57, V. Gopalakrishnan, Self-Shielidng and Energy Dependence of Dilution Cross-Section in the Resolved Resonance Region

IEEE Transactions on Nuclear Power, 1998, Vol. 45, p3184-201, K. Roy, Application of Fault Detection and Identification (FDI) Techniques in Power Regulating Systems of Nuclear Reactors

Annuals of Nuclear Energy, 1999, Vol. 26, p123-40, S.B. Degweker

Accelerator Driven Sub-Critical Systems With Enhanced Neutron Multiplication

Annuals of Nuclear Energy, 1999, Vol. 26, p305-200, S.B. Degweker, Simple Formulae for Interpretation of the Dead Time Alpha (first moment) Method of Reactor Noise