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Volume 75

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Number 1

Table of Contents
Author List(Douglas A. Brownson, Anthony J. Baratta, Gordon E. Robinson, Jose March-Leuba, Yossi Bushlin, Dov Ingman, Y. Segal, Hasna J. Khan, George Kosaly, Masatoshi Nakagawa, M. A. Malik, Wolfgang Beyrich, Werner Golly, Gert Spannagel, Paul De Bièvre, Werner H. Wolters, Willy Lycke, Robert E. Einziger, Robert V. Strain, Hiromichi Fumoto, Shigekazu Sato, Wataru Ito, Takaaki Tamura, Nobuya Yoshiki, Yasutoshi Kobayashi, Cheng-Hsin Mao, Pao-Shan Weng, John K. Wheeler, Alexander Sesonske)
Risk Analysis as a Decision Tool (in German)(Peter-Jörg Jansen)

Effect of Pressurizer Sizing on the Turbine Trip Transient

Douglas A. Brownson, Anthony J. Baratta, Gordon E. Robinson

Nuclear Technology / Volume 75 / Number 1 / October 1986 / Pages 7-14

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT86-A15972

A Reduced-Order Model of Boiling Water Reactor Linear Dynamics

José March-Leuba

Nuclear Technology / Volume 75 / Number 1 / October 1986 / Pages 15-22

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT86-A15973

The Influence of Noise on Edge Determination in Radiography

Yossi Bushlin, Dov Ingman, Y. Segal

Nuclear Technology / Volume 75 / Number 1 / October 1986 / Pages 23-33

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT86-A15974

Subchannel Void Fraction Prediction via Drift-Flux Analysis

Hasna J. Khan, George Kosaly

Nuclear Technology / Volume 75 / Number 1 / October 1986 / Pages 34-45

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT86-A15975

ARKAS: A Three-Dimensional Finite Element Program for the Core-Wide Mechanical Analysis of Liquid-Metal Fast Breeder Reactor Cores

Masatoshi Nakagawa

Nuclear Technology / Volume 75 / Number 1 / October 1986 / Pages 46-65

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT86-A15976

A Long-Term Perspective on the Light Water Reactor Fuel Cycle

M. A. Malik

Nuclear Technology / Volume 75 / Number 1 / October 1986 / Pages 66-72

Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT86-A15977

The Assay of Uranium and Plutonium in Reprocessing Input Solutions by Isotope Dilution Mass Spectrometry: Results of the Isotope Dilution Analysis Measurement Evaluation Programs

Wolfgang Beyrich, Werner Golly, Gert Spannagel, Paul De Bièvre, Werner H. Wolters, Willy Lycke

Nuclear Technology / Volume 75 / Number 1 / October 1986 / Pages 73-81

Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT86-A15978

Behavior of Breached Pressurized Water Reactor Spent-Fuel Rods in an Air Atmosphere Between 250 and 360°C

Robert E. Einziger, Robert V. Strain

Nuclear Technology / Volume 75 / Number 1 / October 1986 / Pages 82-95

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT86-A15979

A Study of Mineral Zeolite as a Nitrogen Oxides Adsorbent for Dissolver Off-Gas Treatment

Hiromichi Fumoto, Shigekazu Sato, Wataru Ito, Takaaki Tamura, Nobuya Yoshiki, Yasutoshi Kobayashi

Nuclear Technology / Volume 75 / Number 1 / October 1986 / Pages 96-108

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT86-A15980

A Driving Device for Activated Wire for Reactor Flux Mapping

Cheng-Hsin Mao, Pao-Shan Weng

Nuclear Technology / Volume 75 / Number 1 / October 1986 / Pages 109-112

Technical Note / Fission Reactor / dx.doi.org/10.13182/NT86-A15981

Sensitivity of Pressurized Water Reactor Source Term Inventory and Decay Power to Core Management Parameters

John K. Wheeler, Alexander Sesonske

Nuclear Technology / Volume 75 / Number 1 / October 1986 / Pages 113-115

Technical Note / Nuclear Safety / dx.doi.org/10.13182/NT86-A15982

Number 2

Table of Contents
Authors(Alex Galperin, Meir Segev, Alvin Radkowsky, B. S. Pei, Y. B. Chen, Chunkuan Shih, W. S. Lin, Kazuki Hida, Sadao Kusuno, Takeshi Seino, John F. Geldard, Adolph L. Beyerlein, Houn-Lin Chiu, B. P. McGrail, Masami Matsuda, Kiyomi Funabashi, Takashi Nishi, Hideo Yusa, Makoto Kikuchi, P. Bhaskar Rao, Om Pal Singh, Manohar S. Sohal, Jae Young Lee, Hee Cheon No, Tatsuhiko Uda, Hisao Otsuka, Yoshihiro Ozawa, Romuald Sulima, Eugene D. Clayton, Hugh K. Clark, Gordon Walker, Richard A. Libby)
Comments on the Dynamics of Fuel Vapor Pressure Buildup in Liquid-Metal Fast Breeder Reactor Core Disruptive Accidents(E. A. Fischer)
Response to “Comments on the Dynamics of Fuel Vapor Pressure Buildup in Liquid-Metal Fast Breeder Reactor Core Disruptive Accidents”(Om Pal Singh, P. Bhaskar Rao)
NBS/NRC Steam Tables: Thermodynamic and Transport Properties and Computer Program for Vapor and Liquid States of Water in SI Units(Efstathios E. Michaelides)
Hazardous Waste Management: In Whose Backyard?(Geoffrey G. Eichholz)
Geology and Radwaste(Geoffrey G. Eichholz)

The Effect of Boron and Gadolinium Burnable Poisons on the Hot-to-Cold Reactivity Swing of a Pressurized Water Reactor Assembly

Alex Galperin, Meir Segev, Alvin Radkowsky

Nuclear Technology / Volume 75 / Number 2 / November 1986 / Pages 123-126

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT86-A33854

Substitution of the Soluble Boron Reactivity Control System of a Pressurized Water Reactor by Gadolinium Burnable Poisons

Alex Galperin, Meir Segev, Alvin Radkowsky

Nuclear Technology / Volume 75 / Number 2 / November 1986 / Pages 127-133

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT86-A33855

Evaluations and Modifications of the EPRI-1 Correlation on PWR Critical Heat Flux Predictions Under Normal and Abnormal Fuel Conditions

B. S. Pei, Y. B. Chen, Chunkuan Shih, W. S. Lin

Nuclear Technology / Volume 75 / Number 2 / November 1986 / Pages 134-147

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT86-A33856

Simultaneous Evaluation of the Effects of ²³²U and ²³⁶U on Uranium Recycling in Boiling Water Reactors

Kazuki Hida, Sadao Kusuno, Takeshi Seino

Nuclear Technology / Volume 75 / Number 2 / November 1986 / Pages 148-159

Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT86-A33857

PUMA — A New Mathematical Model for the Rapid Calculation of Steady- State Concentration Profiles in Mixer-Settler Extraction, Partitioning, and Stripping Contactors Using the Purex Process

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

Nuclear Technology / Volume 75 / Number 2 / November 1986 / Pages 160-167

Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT86-A33858

Waste Package Component Interactions with Savannah River Defense Waste Glass in a Low-Magnesium Salt Brine

B. P. McGrail

Nuclear Technology / Volume 75 / Number 2 / November 1986 / Pages 168-186

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT86-A33859

Decomposition of Ion Exchange Resins by Pyrolysis

Masami Matsuda, Kiyomi Funabashi, Takashi Nishi, Hideo Yusa, Makoto Kikuchi

Nuclear Technology / Volume 75 / Number 2 / November 1986 / Pages 187-192

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT86-A33860

On the Dynamics of Fuel Vapor Pressure Buildup in Voided Liquid-Metal Fast Breeder Reactor Cores During Transient Heating

P. Bhaskar Rao, Om Pal Singh

Nuclear Technology / Volume 75 / Number 2 / November 1986 / Pages 193-195

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT86-A33861

A Radiation Heat Transfer Model for the SCDAP Code

Manohar S. Sohal

Nuclear Technology / Volume 75 / Number 2 / November 1986 / Pages 196-204

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT86-A33862

Three-Dimensional Two-Fluid Code for U-Tube Steam Generator Thermal Design Analysis

Jae Young Lee, Hee Cheon No

Nuclear Technology / Volume 75 / Number 2 / November 1986 / Pages 205-214

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT86-A33863

Characteristics of a Foil-Type Electret Dosimeter for a Surface Alpha Contamination Monitor

Tatsuhiko Uda, Hisao Otsuka, Yoshihiro Ozawa

Nuclear Technology / Volume 75 / Number 2 / November 1986 / Pages 215-221

Technical Paper / Technique / dx.doi.org/10.13182/NT86-A33864

Comparative Study on the Hydrocyclone and the Centrifuge as Emulsion Separators in the HNO₃-H₂O-TBP-Mepasine System

Romuald Sulima*

Nuclear Technology / Volume 75 / Number 2 / November 1986 / Pages 222-224

Technical Note / Chemical Processing / dx.doi.org/10.13182/NT86-A33865

Basis for Extending Limits in ANSI Standard for Mixed Oxides to Heterogeneous Systems

Eugene D. Clayton, Hugh K. Clark, Gordon Walker, Richard A. Libby

Nuclear Technology / Volume 75 / Number 2 / November 1986 / Pages 225-229

Technical Note / Criticality Safety / dx.doi.org/10.13182/NT86-A33866

Number 3

Table of Contents
Authors(William J. Garland, Simon H. Pang, Dov Ingman, Leib Reznik, Samir M. Sami, Mario Dalle Donne, Giacinto P. Tartaglia, Shlomo Ron, Zeev B. Alfassi, Michael Baer, Erich Zimmer, Joachim Borchardt, Budhi Sagar, Paul W. Eslinger, Robert G. Baca, Dhanpat Rai, Janet A. Schramke, Dean A. Moore, Gary L. McVay, Azar P. Majidi, Michael A. Streicher, R. S. Piascik, K. E. Moore)
An Introduction to Nuclear Reactor Theory(E. E. Michaelides)
Technical Reviewers

CANDU-600 Heat Transport System Flow Stability

William J. Garland, Simon H. Pang

Nuclear Technology / Volume 75 / Number 3 / December 1986 / Pages 239-260

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT86-A33840

A Dynamic Reliability Model for Damage Accumulation Processes

Dov Ingman, Leib Reznik

Nuclear Technology / Volume 75 / Number 3 / December 1986 / Pages 261-282

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT86-A33841

A Transient Two-Phase Velocity Difference Model for Drift Calculation in CANDU Thermohydraulic Codes

Samir M. Sami

Nuclear Technology / Volume 75 / Number 3 / December 1986 / Pages 283-297

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT86-A33842