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Volume 78

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Number 1

  • Table of Contents
  • Authors(R. K. S. Rathore, P. Munshi I. D. Dhariyal S. T. Swamy, R. Muralidharan, V. K. Chexal, Warren F. Witzig, Sunil D. Weerakkody, Edward C. Beahm, Yun-ming Wang, Simon J. Wisbey, William E. Shockley, Sunil D. Weerakkody, Warren F. Witzig, Alfred W. Reed, Herbert Meister, Daniel J. Sasmor, Masami Matsuda, Kiyomi Funabashi, Fumio Kawamura, Shunsuke Uchida, Katsumi Ohsumi, Keshav Chander, Bharatkumar N. Patil, Jayshree V. Kamat, Nandakumar B. Khedekar, Remani B. Manolkar, Surendranath G. Marathe, Aaron Barkatt, Karen A. Michael, William Sousanpour, Alisa Barkatt, L. Miguel Penafiel, Pedro B. Macedo, Herbert G. Sutter, D. J. Sherwood, A. L. Ward, G. D. Johnson)

Tomographic Reconstruction of the Density Field Using Radial Polynomials

R. K. S. Rathore, P. Munshi, I. D. Dhariyal, S. T. Swamy

Nuclear Technology / Volume 78 / Number 1 / July 1987 / Pages 7-12

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT87-A34003

Increasing Diesel Start Time for a Boiling Water Reactor (BWR/6) Using the New Emergency Core Cooling System Approach

R. Muralidharan, V. K. Chexal

Nuclear Technology / Volume 78 / Number 1 / July 1987 / Pages 13-23

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT87-A34004

Evacuation Risks: Quantification and Application to Evacuation Scenarios of Nuclear Power Plants

Warren F. Witzig, Sunil D. Weerakkody

Nuclear Technology / Volume 78 / Number 1 / July 1987 / Pages 24-33

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT87-A34005

Organic Iodide Formation During Severe Accidents in Light Water Nuclear Reactors

Edward C. Beahm, Yun-Ming Wang, Simon J. Wisbey, William E. Shockley

Nuclear Technology / Volume 78 / Number 1 / July 1987 / Pages 34-42

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT87-A34006

A Rational Model for the Off-Site Protective Action Selection During Nuclear Reactor Accidents

Sunil D. Weerakkody, Warren F. Witzig

Nuclear Technology / Volume 78 / Number 1 / July 1987 / Pages 43-53

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT87-A34007

Measurements of Capillary Pressure in Urania Debris Beds

Alfred W. Reed, Herbert Meister, Daniel J. Sasmor

Nuclear Technology / Volume 78 / Number 1 / July 1987 / Pages 54-61

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT87-A34008

Application of Carboxylic Acid Cation Exchange Resin to Water Purification in Nuclear Power Plants

Masami Matsuda, Kiyomi Funabashi, Fumio Kawamura, Shunsuke Uchida, Katsumi Ohsumi

Nuclear Technology / Volume 78 / Number 1 / July 1987 / Pages 62-68

Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT87-A34009

Direct Dissolution of Nuclear Materials for Chemical Quality Control

Keshav Chander, Bharatkumar N. Patil, Jayshree V. Kamat, Nandakumar B. Khedekar, Remani B. Manolkar, Surendranath G. Marathe

Nuclear Technology / Volume 78 / Number 1 / July 1987 / Pages 69-74

Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT87-A34010

Properties of Novel Selective Ion Exchangers for Nuclear Plant Applications

Aaron Barkatt, Karen A. Michael, William Sousanpour, Alisa Barkatt, L. Miguel Penafiel, Pedro B. Macedo, Herbert G. Sutter

Nuclear Technology / Volume 78 / Number 1 / July 1987 / Pages 75-82

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT87-A34011

Development of Materials for Fast Reactor Fuel Assemblies

D. J. Sherwood, A. L. Ward, G. D. Johnson

Nuclear Technology / Volume 78 / Number 1 / July 1987 / Pages 83-89

Technical Paper / Material / dx.doi.org/10.13182/NT87-A34012

Number 2

A Three-Field Diffusion Model of Three-Phase, Three-Component Flow for the Transient Three-Dimensional Computer Code IVA2/001

Nicolay Ivanov Kolev

Nuclear Technology / Volume 78 / Number 2 / August 1987 / Pages 95-131

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT87-A33990

Real-Time Stability Monitoring Method for Boiling Water Reactor Nuclear Power Plants

Kohyu Fukunishi, Satoshi Suzuki

Nuclear Technology / Volume 78 / Number 2 / August 1987 / Pages 132-139

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT87-A33991

Analysis of Ex-Core Detector Response Measured During Nuclear Ship Mutsu Land-Loaded Core Critical Experiment

Masafumi Itagaki, Jun-Ichi Abe, Katsuaki Kuribayashi

Nuclear Technology / Volume 78 / Number 2 / August 1987 / Pages 140-150

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT87-A33992

Rapid Calculation of Steady-State Concentration Profiles with Nonequilibrium Mass Transfer in Contactors Using the Purex Process

John F. Geldard, Adolph L. Beyerlein, Houn-Lin Chiu

Nuclear Technology / Volume 78 / Number 2 / August 1987 / Pages 151-156

Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT87-A33993

Experimental Studies of Fission Product Release from Commercial Light Water Reactor Fuel Under Accident Conditions

Morris F. Osborne, Jack L. Collins, Richard A. Lorenz

Nuclear Technology / Volume 78 / Number 2 / August 1987 / Pages 157-169

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT87-A33994

The Impact of Heat Transfer Models on Core/Concrete Interaction

Lainsu Kao, Mujid S. Kazimi

Nuclear Technology / Volume 78 / Number 2 / August 1987 / Pages 170-184

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT87-A33995

Stability of Cement-Glass Packages Containing Sodium Borate Salt Generated from Pressurized Water Reactor Power Plants

Tatsuo Izumida, Fumio Kawamura, Koichi Chino, Makoto Kikuchi

Nuclear Technology / Volume 78 / Number 2 / August 1987 / Pages 185-190

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT87-A33996

The Recycle Value of Fuel Discharged from Light Water Reactors

Nasir Majid Mirza, Ansar Parvez

Nuclear Technology / Volume 78 / Number 2 / August 1987 / Pages 191-196

Technical Note / Fuel Cycle / dx.doi.org/10.13182/NT87-A33997

Number 3

  • Table of Contents
  • Author List(Makoto Takano, Kazuhiro Sawa, Takao Hayashi, Wulf Bürkle, Walter H. Köhler, Friedrich H. Morgenstern, Helmut Rothfuss, Friedhelm Vogt, Kurt Vinzens, Horst Kappauf, Arie Johannes Van ’t Hoft, Jacob Johan de Jong, Jan Piet Vroom, Gerhard Robert Küpers, Willi K. Biermann, Hans-Jochen Heuvel, Servais Pilate, Yvon Vanderborck, Eduard Pelckmans, Guido Vanhellemont, Horst Roepenack, Wolfgang Stoll, Dieter Althaus, Nicolas Brahy, Edward C. Beahm, Victor R. Prybutok, Leonard M. Gold, Marcus H. Voth, Warren F. Witzig, Francis Barbry, Raymond Prigent)

A Design Method to Isothermalize the Core of High-Temperature Gas-Cooled Reactors

Makoto Takano, Kazuhiro Sawa

Nuclear Technology / Volume 78 / Number 3 / September 1987 / Pages 207-215

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT87-A15986

Comparison of Heat Transport Capability of a Steam Generator (SG) in a High-Temperature Gas-Cooled Reactor with That of an SG in Other Types of Reactors

Takao Hayashi

Nuclear Technology / Volume 78 / Number 3 / September 1987 / Pages 216-226

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT87-A15987

Preface: Nuclear Power Plant Kalkar (SNR-300)

Wulf Bürkle, Walter H. Köhler

Nuclear Technology / Volume 78 / Number 3 / September 1987 / Pages 229-230

Nuclear Power Plant Kalkar (SNR-300) / dx.doi.org/10.13182/NT87-A15988

Kalkar Nuclear Power Plant (SNR-300)—A Sodium-Cooled Fast Breeder Reactor Prototype

Friedrich H. Morgenstern

Nuclear Technology / Volume 78 / Number 3 / September 1987 / Pages 231-244

Nuclear Power Plant Kalkar (SNR-300) / Fission Reactor / dx.doi.org/10.13182/NT87-A15989

Reactor Vessel System

Helmut Rothfuss, Friedhelm Vogt

Nuclear Technology / Volume 78 / Number 3 / September 1987 / Pages 245-254

Nuclear Power Plant Kalkar (SNR-300) / Fission Reactor / dx.doi.org/10.13182/NT87-A15990

Primary and Secondary Main Piping Systems

Kurt Vinzens, Horst Kappauf

Nuclear Technology / Volume 78 / Number 3 / September 1987 / Pages 255-261

Nuclear Power Plant Kalkar (SNR-300) / Fission Reactor / dx.doi.org/10.13182/NT87-A15991

Fabrication of Intermediate Heat Exchangers, Steam Generators, and Sodium Pumps for SNR-300

Arie Johannes Van ’t Hoft, Jacob Johan de Jong, Jan Piet Vroom, Gerhard Robert Küpers

Nuclear Technology / Volume 78 / Number 3 / September 1987 / Pages 262-277

Nuclear Power Plant Kalkar (SNR-300) / Fission Reactor / dx.doi.org/10.13182/NT87-A15992

Fabrication of Fuel Elements Interplay Between Typical SNR Mark la Specifications and the Fuel Element Fabrication

Willi K. Biermann, Hans-Jochen Heuvel, Servais Pilate, Yvon Vanderborck, Eduard Pelckmans, Guido Vanhellemont, Horst Roepenack, Wolfgang Stoll

Nuclear Technology / Volume 78 / Number 3 / September 1987 / Pages 278-283

Nuclear Power Plant Kalkar (SNR-300) / Fission Reactor / dx.doi.org/10.13182/NT87-A15993

Refueling System Fabrication and Testing

Dieter Althaus, Nicolas Brahy

Nuclear Technology / Volume 78 / Number 3 / September 1987 / Pages 284-294

Nuclear Power Plant Kalkar (SNR-300) / Fission Reactor / dx.doi.org/10.13182/NT87-A15994

Tellurium Behavior in Containment Under Light Water Reactor Accident Conditions

Edward C. Beahm

Nuclear Technology / Volume 78 / Number 3 / September 1987 / Pages 295-302

Nuclear Power Plant Kalkar (SNR-300) / Nuclear Safety / dx.doi.org/10.13182/NT87-A15995

Modeling for Comparison of Leukemia Incidence Risk Between Nuclear and Coal Power Industries

Victor R. Prybutok, Leonard M. Gold

Nuclear Technology / Volume 78 / Number 3 / September 1987 / Pages 303-311

Nuclear Power Plant Kalkar (SNR-300) / Nuclear Safety / dx.doi.org/10.13182/NT87-A15996

Determination of Optimum Alternative Low-Level Radioactive Waste Disposal Site/Disposal Technology Combinations

Marcus H. Voth, Warren F. Witzig

Nuclear Technology / Volume 78 / Number 3 / September 1987 / Pages 312-319

Nuclear Power Plant Kalkar (SNR-300) / Radioactive Waste Management / dx.doi.org/10.13182/NT87-A15997

The EDAC System and New Developments Under Consideration at the Commissariat à I’Energie Atomique for Criticality Accident Detection

Francis Barbry, Raymond Prigent

Nuclear Technology / Volume 78 / Number 3 / September 1987 / Pages 320-325

Nuclear Power Plant Kalkar (SNR-300) / Criticality Safety / dx.doi.org/10.13182/NT87-A15998