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Volume 70

Number 1 | Number 2 | Number 3

Number 1

  • Table of Contents
  • Authors(Lance J. Agee, Jorge Arpa, Alan S. Fatemi, S. K. Mathavan, Bruce E. Schmitt, E. D. Hughes, K. R. Katsma, M. P. Paulsen, G. D. Miller, J. G. Refling, A. J. Roscioli, S. A. Somma, C. A. Kukielka, L. M. Olson, Ernest V. Moore, S. F. Deng, K. K. Chitkara, B. B. Chu, Adel Alapour, Robert A. Hommerson, Craig E. Peterson, V. K. (Bindi) Chexal, William H. Layman, Richard D. Hentzen, Garry C. Gose, Richard F. Farman, Charles E. Hendrix, Jason Chao, Yine-Ping Ting, Craig E. Peterson, V. K. (Bindi) Chexal, Talmage B. Clements, M. A. Alammar, Norman T. Simms, Vincent P. Manno, Michael W. Golay, Terry F. Rees, Jess M. Cleveland, Kenneth L. Nash)

RETRAN Overview

Lance J. Agee

Nuclear Technology / Volume 70 / Number 1 / July 1985 / Pages 7-16

Overview / Third International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT85-A33658

RETRAN Applications in Pressurized Thermal Shock Analysis of Turkey Point Units 3 and 4

Jorge Arpa, Alan S. Fatemi, S. K. Mathavan

Nuclear Technology / Volume 70 / Number 1 / July 1985 / Pages 17-25

Technical Paper / Third International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT85-A33659

RETRAN Analysis of the Hanford N Reactor for a Loss of Feedwater

Bruce E. Schmitt

Nuclear Technology / Volume 70 / Number 1 / July 1985 / Pages 26-29

Technical Paper / Third International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT85-A33660

Semi-Implicit Solution Methods for the RETRAN Model Equations

E. D. Hughes, K. R. Katsma, M. P. Paulsen

Nuclear Technology / Volume 70 / Number 1 / July 1985 / Pages 30-41

Technical Paper / Third International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT85-A33661

Engineering Analysis Activities in Support of Susquehanna Unit 1 Startup Testing and Cycle 1 Operations

G. D. Miller, J. G. Refling, A. J. Roscioli, S. A. Somma, C. A. Kukielka, L. M. Olson

Nuclear Technology / Volume 70 / Number 1 / July 1985 / Pages 42-52

Technical Paper / Third International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT85-A33662

RETRAN Analysis of Boiling Water Reactor Accidents

Ernest V. Moore, S. F. Deng, K. K. Chitkara, B. B. Chu

Nuclear Technology / Volume 70 / Number 1 / July 1985 / Pages 53-63

Technical Paper / Third International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT85-A33663

Analysis of Hatch-2 Dual Recirculation Pump Trip Startup Test

Adel Alapour, Robert A. Hommerson

Nuclear Technology / Volume 70 / Number 1 / July 1985 / Pages 64-73

Technical Paper / Third International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT85-A33664

An Investigation of Decreasing Reactor Coolant Inventory as a Mechanism to Reduce Power During a Boiling Water Reactor Anticipated Transient Without Scram

Craig E. Peterson, V. K. (Bindi) Chexal, William H. Layman, Richard D. Hentzen, Garry C. Gose

Nuclear Technology / Volume 70 / Number 1 / July 1985 / Pages 74-83

Technical Paper / Third International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT85-A33665

RETRAN-02 Analysis of Loss-of-Fluid Test Experiments L9-3 and L9-4

Richard F. Farman, Charles E. Hendrix, Jason Chao

Nuclear Technology / Volume 70 / Number 1 / July 1985 / Pages 84-93

Technical Paper / Third International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT85-A33666

RETRAN Analysis of the San Onofre Unit 2 Turbine Trip from 100% Power

Yine-Ping Ting

Nuclear Technology / Volume 70 / Number 1 / July 1985 / Pages 94-103

Technical Paper / Third International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT85-A33667

Analysis of a Hot-Leg Small Break Loss-of-Coolant Accident in a Three-Loop Westinghouse Pressurized Water Reactor Plant

Craig E. Peterson, V. K. (Bindi) Chexal, Talmage B. Clements

Nuclear Technology / Volume 70 / Number 1 / July 1985 / Pages 104-110

Technical Paper / Third International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT85-A33668

Comparison of RETRAN and RELAP5 Models to Oyster Creek Loss of Feedwater Transient

M. A. Alammar

Nuclear Technology / Volume 70 / Number 1 / July 1985 / Pages 111-119

Technical Paper / Third International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT85-A33669

RETRAN-02 Comparison of Natural Circulation Flow Rates at Babcock & Wilcox 177-FA Plants

Norman T. Simms

Nuclear Technology / Volume 70 / Number 1 / July 1985 / Pages 120-123

Technical Paper / Third International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT85-A33670

Analytical Investigation of Postaccident Containment Atmospheric Stratification

Vincent P. Manno, Michael W. Golay

Nuclear Technology / Volume 70 / Number 1 / July 1985 / Pages 124-132

Technical Paper / Third International Retran Meeting / Nuclear Safety / dx.doi.org/10.13182/NT85-A33671

Leaching of Plutonium from a Radioactive Waste Glass by Eight Groundwaters from the Western United States

Terry F. Rees, Jess M. Cleveland, Kenneth L. Nash

Nuclear Technology / Volume 70 / Number 1 / July 1985 / Pages 133-140

Technical Paper / Third International Retran Meeting / Radioactive Waste Management / dx.doi.org/10.13182/NT85-A33672

Number 2

  • Table of Contents
  • Authors(H. Deuber, H. Deuber, K. Gerlach, Åke H. Persson, H. Deuber, K. Gerlach, R. Kaempffer, Howard A. Larson, William F. Booty, Donald R. Chick, Lynn J. Christensen, Robert J. Forrester, J. W. Sielinsky, Katsuyuki Kawashima, Kotaro Inoue, Kunikazu Kaneto, Tatsutoshi Inagaki, Mitsuhiro Suzuki, Kanji Tasaka, Yoshinari Anoda, Hiroshige Kumamaru, Hideo Nakamura, Masayoshi Shiba, V. K. Gupta, Ramesh K. Kapoor, J.-J. Huet, L. Coheur, A. De Bremaecker, L. De Wilde, J. Gedopt, W. Hendrix, W. Vandermeulen, Kazuo Haga, Yoshihiro Kikuchi, Seichi Sato, Hirotaka Furuya, Yuji Nishino, Masayasu Sugisaki, Tsunetaka Banba, Takashi Murakami, Tatsuo Izumida, Koji Kato, Fumio Kawamura, Hideo Yusa, Yoshimasa Yamamoto, Yukihiko Komatsu, Minoru Harada, Trygve E. Eriksen, Ian J. Hastings, David R. McCracken, Elio Mizzan, Roger D. Barrand, John R. Kelm, Ken E. Nash, J. Novak, William E. Loewe, A. R. Wazzan, A. Villalobos, D. Okrent, Max Furrer, Robin C. Cripps, Reinhard Gubler)

Investigations on the Improvement of the Iodine Filtration Concept of Boiling Water Reactors

H. Deuber

Nuclear Technology / Volume 70 / Number 2 / August 1985 / Pages 149-152

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT85-A33637

Investigations on the Testing of Iodine Filters by Different Methods

H. Deuber, K. Gerlach

Nuclear Technology / Volume 70 / Number 2 / August 1985 / Pages 153-157

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT85-A33638

The Filtered Venting System Under Construction at Barsebäck

Åke H. Persson

Nuclear Technology / Volume 70 / Number 2 / August 1985 / Pages 158-160

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT85-A33639

Investigations on the Aging of Activated Carbons in the Exhaust Air of a Pressurized Water Reactor

H. Deuber, K. Gerlach, R. Kaempffer

Nuclear Technology / Volume 70 / Number 2 / August 1985 / Pages 161-166

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT85-A33640

Installation of Automatic Control at Experimental Breeder Reactor II

Howard A. Larson, William F. Booty, Donald R. Chick, Lynn J. Christensen, Robert J. Forrester, J. W. Sielinsky

Nuclear Technology / Volume 70 / Number 2 / August 1985 / Pages 167-179

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT85-A33641

Control Rod Worth and Related Nuclear Characteristics of an Axially Heterogeneous Liquid-Metal Fast Breeder Reactor Core

Katsuyuki Kawashima, Kotaro Inoue, Kunikazu Kaneto, Tatsutoshi Inagaki

Nuclear Technology / Volume 70 / Number 2 / August 1985 / Pages 180-188

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT85-A33642

Recirculation Pump Discharge Line Break Tests at ROSA-III for a Boiling Water Reactor

Mitsuhiro Suzuki, Kanji Tasaka, Yoshinari Anoda, Hiroshige Kumamaru, Hideo Nakamura, Masayoshi Shiba

Nuclear Technology / Volume 70 / Number 2 / August 1985 / Pages 189-203

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT85-A33643

Reducing the Consequences of Reactor Accidents with a Green Belt

V. K. Gupta, Ramesh K. Kapoor

Nuclear Technology / Volume 70 / Number 2 / August 1985 / Pages 204-214

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT85-A33644

Fabrication and Mechanical Properties of Oxide Dispersion Strengthening Ferritic Alloy Canning Tubes for Fast Reactor Fuel Pins

J.-J. Huet, L. Coheur, A. De Bremaecker, L. De Wilde, J. Gedopt, W. Hendrix, W. Vandermeulen

Nuclear Technology / Volume 70 / Number 2 / August 1985 / Pages 215-219

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT85-A33645

Experimental Investigation of Coolability Degradation by Fission Gas Release into Flowing Sodium in a Fuel Pin Bundle

Kazuo Haga, Yoshihiro Kikuchi

Nuclear Technology / Volume 70 / Number 2 / August 1985 / Pages 220-234

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT85-A33646

Thermal Conductivity of Simulated Radioactive Waste Glass

Seichi Sato, Hirotaka Furuya, Yuji Nishino, Masayasu Sugisaki

Nuclear Technology / Volume 70 / Number 2 / August 1985 / Pages 235-242

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT85-A33647

The Leaching Behavior of a Glass Waste Form —Part II: The Leaching Mechanisms

Tsunetaka Banba, Takashi Murakami

Nuclear Technology / Volume 70 / Number 2 / August 1985 / Pages 243-248

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT85-A33648

Electrolytic Decontamination of Surface-Contaminated Metal by Alternating Electrolysis Using Square-Wave Current in a Neutral Salt Electrolyte

Tatsuo Izumida, Koji Kato, Fumio Kawamura, Hideo Yusa

Nuclear Technology / Volume 70 / Number 2 / August 1985 / Pages 249-253

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT85-A33649

A Consolidation Process for Spent Burnable Poison Rod Assemblies

Yoshimasa Yamamoto, Yukihiko Komatsu, Minoru Harada

Nuclear Technology / Volume 70 / Number 2 / August 1985 / Pages 254-260

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT85-A33650

A Laboratory Study on Radionuclide Migration in Single Natural Granitic Fissures

Trygve E. Eriksen

Nuclear Technology / Volume 70 / Number 2 / August 1985 / Pages 261-267

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT85-A33651

Postirradiation Dimensional Stability and Fission Product Behavior of Deliberately Defected UO2 Fuel at 200 and 400°C

Ian J. Hastings, David R. McCracken, Elio Mizzan, Roger D. Barrand, John R. Kelm, Ken E. Nash, J. Novak

Nuclear Technology / Volume 70 / Number 2 / August 1985 / Pages 268-273

Technical Paper / Material / dx.doi.org/10.13182/NT85-A33652

Initial Radiations from Tactical Nuclear Weapons

William E. Loewe

Nuclear Technology / Volume 70 / Number 2 / August 1985 / Pages 274-284

Technical Paper / Radiation Biology and Environment / dx.doi.org/10.13182/NT85-A33653

The Effect of Re-Solution Models on Fission Gas Disposition in Irradiated UO2 Fuel

A. R. Wazzan, A. Villalobos, D. Okrent

Nuclear Technology / Volume 70 / Number 2 / August 1985 / Pages 285-289

Technical Note / Fission Reactor / dx.doi.org/10.13182/NT85-A33654

Measurement of the Iodine Partition Coefficient

Max Furrer, Robin C. Cripps, Reinhard Gubler

Nuclear Technology / Volume 70 / Number 2 / August 1985 / Pages 290-293

Technical Note / Nuclear Safety / dx.doi.org/10.13182/NT85-A33655

Number 3

Authors

Hiroshi Fukui, Kaichiro Mishima, Seiji Shiroya, Masatoshi Hayashi, Keiji Kanda, Yasuhide Senda, Yasuhide Senda, Seiji Shiroya, Masatoshi Hayashi, Keiji Kanda, N. Abe, M. Kato, H. Nagasaka, Jiro Wakabayashi, Shin-ichi Tashima, Akio Gofuku, Alex Galperin, Meir Segev, Anatoly Goldfeld, Yonathan Karni, Y. F. Chang, P. C. Watson, M. D. Langan, P. Sermer, Robert P. Wichner, Roger D. Spence, John F. Geldard, Leigh Phillips, Adolph L. Beyerlein, Karl Richter, Jean Gueugnon, Gerard Kramer, Carlo Sari, Paul Werner, Roberto Caponetti, John R. Krsul, Robert A. Washburn, Bernard L. Cohen

Nuclear Technology / Volume 70 / Number 3 / September 1985 / Pages 295-300

Department / dx.doi.org/10.13182/NT85-A15957

Effect of Reducing Fuel Enrichment on the Void Reactivity — Part I: Experimental Study

Hiroshi Fukui, Kaichiro Mishima, Seiji Shiroya, Masatoshi Hayashi, Keiji Kanda, Yasuhide Senda

Nuclear Technology / Volume 70 / Number 3 / September 1985 / Pages 301-317

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT85-A15958

Effect of Reducing Fuel Enrichment on the Void Reactivity — Part II: Analytical Study

Yasuhide Senda, Seiji Shiroya, Masatoshi Hayashi, Keiji Kanda

Nuclear Technology / Volume 70 / Number 3 / September 1985 / Pages 318-334

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT85-A15959

Analysis of Upper Plenum Level Oscillatory Phenomena by TRAC-BD1

N. Abe, M. Kato, H. Nagasaka

Nuclear Technology / Volume 70 / Number 3 / September 1985 / Pages 335-342

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT85-A15960

Two Identification Techniques for Disturbance Diagnosis in Nuclear Power Plants

Jiro Wakabayashi, Shin-Ichi Tashima, Akio Gofuku

Nuclear Technology / Volume 70 / Number 3 / September 1985 / Pages 343-353

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT85-A15961

BGUCORE — A Computational System for Neutronic Analysis of a Pressurized Water Reactor Core

Alex Galperin, Meir Segev, Anatoly Goldfeld, Yonathan Karni

Nuclear Technology / Volume 70 / Number 3 / September 1985 / Pages 354-363

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT85-A15962

Bruce Nuclear Generating Station B Rapid Cooldown Test and Validation of Simulation Model

Y. F. Chang, P. C. Watson, M. D. Langan, P. Sermer

Nuclear Technology / Volume 70 / Number 3 / September 1985 / Pages 364-375

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT85-A15963

A Chemical Equilibrium Estimate of the Aerosols Produced in an Overheated Light Water Reactor Core

Robert P. Wichner, Roger D. Spence

Nuclear Technology / Volume 70 / Number 3 / September 1985 / Pages 376-393

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT85-A15964

Correlation Functions for the Distribution Coefficients of U(IV) and Pu(III) Ions Between Aqueous Nitric Acid and 30% TBP in an Aliphatic Diluent

John F. Geldard, Leigh Phillips, Adolph L. Beyerlein

Nuclear Technology / Volume 70 / Number 3 / September 1985 / Pages 394-400

Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT85-A15965

Direct Pressing: A New Method of Fabricating MX Fuel Pellets

Karl Richter, Jean Gueugnon, Gerard Kramer, Carlo Sari, Paul Werner

Nuclear Technology / Volume 70 / Number 3 / September 1985 / Pages 401-407

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT85-A15966

Sodium Cleaning Procedures for PEC Prototype Mechanisms

Roberto Caponetti

Nuclear Technology / Volume 70 / Number 3 / September 1985 / Pages 408-423

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT85-A15967

Removal of Radioactive Sodium from Experimental Breeder Reactor-II Components and Conversion to a Disposable Solid Waste: Alcohol Recovery

John R. Krsul, Robert A. Washburn

Nuclear Technology / Volume 70 / Number 3 / September 1985 / Pages 424-432

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT85-A15968

Critique of the National Academy of Sciences Study of the Isolation System for Geologic Disposal of Radioactive Waste

Bernard L. Cohen

Nuclear Technology / Volume 70 / Number 3 / September 1985 / Pages 433-440

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT85-A15969

 
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