ANS / Publications / Journals / Nuclear Technology

The Current Status of Theoretically Based Approaches to the Prediction of the Critical Heat Flux in Flow Boiling

Joel Weisman

Nuclear Technology / Volume 99 / Number 1 / July 1992 / Pages 1-21

Critical Review / dx.doi.org/10.13182/NT92-A34699

Basic Philosophy of the Safety Design of the Toshiba Boiling Water Reactor

Takashi Sato

Nuclear Technology / Volume 99 / Number 1 / July 1992 / Pages 22-35

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT92-A34700

Use of Artificial Neural Networks to Analyze Nuclear Power Plant Performance

Zhichao Guo, Robert E. Uhrig

Nuclear Technology / Volume 99 / Number 1 / July 1992 / Pages 36-42

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT92-A34701

Containment Pressurization and Burning of Combustible Gases in a Large, Dry PWR Containment During a Station Blackout Sequence

Min Lee, Chen Tsung Fan

Nuclear Technology / Volume 99 / Number 1 / July 1992 / Pages 43-57

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT92-A34702

Delayed Neutron Noise Characteristics of an In-Pile Fission Product Loop

Tetsuo Tamaoki, Takuhiko Sakai, Hiroshi Endo, Kazuo Haga, Ryoichi Takahashi

Nuclear Technology / Volume 99 / Number 1 / July 1992 / Pages 58-69

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT92-A34703

The Iodine Species and Their Behavior in the Dissolution of Spent-Fuel Specimens

Tsutomu Sakurai, Akira Takahashi, Niroh Ishikawa, Yoshihide Komaki, Mamoru Ohnuki, Takeo Adachi

Nuclear Technology / Volume 99 / Number 1 / July 1992 / Pages 70-79

Technical Paper / Enrichment and Reprocessing System / dx.doi.org/10.13182/NT92-A34704

A Model for Sound Velocity in a Two-Phase Air-Water Bubbly Flow

Nien-Mien Chung, Wei-Keng Lin, Bau-Shei Pei, Yih-Yun Hsu

Nuclear Technology / Volume 99 / Number 1 / July 1992 / Pages 80-89

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT92-A34705

Thermal-Hydraulic Characteristics of Coolant in the Core Bottom Structure of the High-Temperature Engineering Test Reactor

Yoshiyuki Inagaki, Kazuhiko Kunitomi, Yoshiaki Miyamoto, Ikuo Ioka, Kunihiko Suzuki

Nuclear Technology / Volume 99 / Number 1 / July 1992 / Pages 90-103

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT92-A34706

Study of Void Fraction and Mixing of Immiscible Liquids in a Pool Configuration by an Upward Gas Flow

Joan-Carles Casas, Michael L. Corradini

Nuclear Technology / Volume 99 / Number 1 / July 1992 / Pages 104-119

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT92-A34707

An Integrated Operator Decision Aid System for Boiling Water Reactor Power Plants

Shigeki Fukutomi, Norio Naito, Yoji Takizawa

Nuclear Technology / Volume 99 / Number 1 / July 1992 / Pages 120-132

Technical Paper / Reactor Operation / dx.doi.org/10.13182/NT92-A34708

A Study of Thermal-Hydraulic Requirements for Increasing the Power Rates for Natural-Circulation Boiling Water Reactors

Akira Yasuo, Fumio Inada, Masataka Hidaka

Nuclear Technology / Volume 99 / Number 2 / August 1992 / Pages 135-141

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT92-A34684

The Use of Influence Diagrams for Evaluating Severe Accident Management Strategies

Moosung Jae, George E. Apostolakis

Nuclear Technology / Volume 99 / Number 2 / August 1992 / Pages 142-157

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT92-A34685

Seismic Study of High-Temperature Engineering Test Reactor Core Graphite Structures

Tatsuo Iyoku, Yoshiyuki Inagaki, Shusaku Shiozawa, Isoharu Nishiguchi

Nuclear Technology / Volume 99 / Number 2 / August 1992 / Pages 158-168

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT92-A34686

Seismic Response of the High-Temperature Engineering Test Reactor Core Bottom Structure

Tatsuo Iyoku, Yoshiyuki Inagaki, Shusaku Shiozawa, Masatoshi Futakawa, Toshiyo Miki

Nuclear Technology / Volume 99 / Number 2 / August 1992 / Pages 169-176

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT92-A34687

COBRA/RELAP5: A Merged Version of the COBRA-TF and RELAP5/MOD3 Codes

Sang Yong Lee, Jae Jun Jeong, Si-Hwan Kim, Soon Heung Chang

Nuclear Technology / Volume 99 / Number 2 / August 1992 / Pages 177-187

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT99-177

Manned Mars Rover Powered by a Nuclear Reactor: Radiation Shield Analysis

Nicholas J. Morley, Mohamed S. El-Genk

Nuclear Technology / Volume 99 / Number 2 / August 1992 / Pages 188-202

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT92-A34689

MELCOR Modeling of the National Research Universal Full-Length High-Temperature 2 Experiment

Imtiaz K. Madni, Xiao-Dong Guo

Nuclear Technology / Volume 99 / Number 2 / August 1992 / Pages 203-212

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT92-A34690

Determination of Low Activities Released by a Decommissioned Fuel Fabrication Plant Through Natural Air Exchange

Bernd Sohnius, Rudolf Anton, Erwin Wehner, Frank-Dietrich Heidt, Rudolf Rabenstein

Nuclear Technology / Volume 99 / Number 2 / August 1992 / Pages 213-221

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT92-A34691

Benchmark of CASMO-3/ SIMULATE-3 with a New Modeling for the Chinshan and Kuosheng Boiling Water Reactors

Pin-Wu Kao, Jing-Tong Yang, Chian-Yeh Ho, Cheng-Hsien Chou, Ruey-Chang Huang, and, Ta-Chieh Sun

Nuclear Technology / Volume 99 / Number 2 / August 1992 / Pages 222-234

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT92-A34692

Destruction of Emulsions Stabilized by Precipitates of Zirconium and Tributyl Phosphate Degradation Products

Hiroshi Sugai, Kenzo Munakata

Nuclear Technology / Volume 99 / Number 2 / August 1992 / Pages 235-241

Technical Paper / Enrichment and Reprocessing System / dx.doi.org/10.13182/NT92-A34693

Corrosion Behavior of Silicon Nitride, Magnesium Oxide, and Several Metals in Molten Calcium Chloride with Chlorine

David F. Mclaughlin, Charles E. Sessions, John E. Marra

Nuclear Technology / Volume 99 / Number 2 / August 1992 / Pages 242-251

Technical Paper / Enrichment and Reprocessing System / dx.doi.org/10.13182/NT92-A34694

Detection of Parts-Per-Million Levels of Hydrogen in Solids Using a Modified Notched Neutron Spectrum Technique

William H. Miller, Li-Te Lin, Robert M. Brugger, Walter Meyer

Nuclear Technology / Volume 99 / Number 2 / August 1992 / Pages 252-257

Technical Paper / Material / dx.doi.org/10.13182/NT92-A34695

A Model for Sound Velocity and Its Relationship with Interfacial Area in a Steam-Water, Two-Phase Bubbly Flow

Nien-Mien Chung, Wei-Keng Lin, Bau-Shei Pei, Dong-Jye Li, Yih-Yun Hsu†

Nuclear Technology / Volume 99 / Number 2 / August 1992 / Pages 258-267

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT92-A34696

Numerical Solution for the Nonlinear Diffusion Equation Describing the Transport of Volatile Fission Products in Nuclear Fuels

Conor O’Carroll, Klaus Lassmann

Nuclear Technology / Volume 99 / Number 2 / August 1992 / Pages 268-273

Technical Note / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT92-A34697

Results of an Investigation of Safety Improvement and Service Life Prolongation of the BOR-60 Experimental Reactor

Vladimir N. Efimov, Gadzhy I. Gadzhiev, Arcady A. Minakov

Nuclear Technology / Volume 99 / Number 3 / September 1992 / Pages 275-279

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT92-A34711

Power Instability and Stochastic Dynamics of Periodic Pulsed Reactors

Evgueny P. Shabalin

Nuclear Technology / Volume 99 / Number 3 / September 1992 / Pages 280-288

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT92-A34712

The In-Pile Local Blockage Experiments Mol-7C/6 and 7 — Results and Preliminary Interpretation

Karl Schleisiek, Jürgen Aberle, Siegfried Jacobi, August Rahn, Lothar Schmidt, Gilbert Vanmassenhove, Alfons Verwimp

Nuclear Technology / Volume 99 / Number 3 / September 1992 / Pages 289-300

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT92-A34713

QUASAR — A Computer Code for Analyzing Subassembly Accidents in Liquid-Metal Fast Breeder Reactors

Fumio Kasahara, Hiroshi Endo

Nuclear Technology / Volume 99 / Number 3 / September 1992 / Pages 301-308

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT92-A34714

Freezing Phenomena of Ceramic Alumina Melts Flowing in Pin Bundles

Günter Fieg, Manfred Möschke, Heinrich Werle

Nuclear Technology / Volume 99 / Number 3 / September 1992 / Pages 309-317

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT92-A34715

Passive Safety Features of a Bottom-Supported Fast Breeder Reactor Vessel

Hiroshi Endo, Yoshio Kumaoka, Simcha Golan, Hiroshi Nakagawa

Nuclear Technology / Volume 99 / Number 3 / September 1992 / Pages 318-329

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT92-A34716

Release Kinetics of Volatile Fission Products Under Severe Accident Conditions

Brent J. Lewis, Fernando C. Iglesias, C. E. Laurence Hunt, David S. Cox

Nuclear Technology / Volume 99 / Number 3 / September 1992 / Pages 330-342

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT92-A34717

Quantitative Studies of Severe Fuel Damage Using Delayed Neutron Data

Theodore H. Bauer, Thomas H. Braid, Karl Schleisiek

Nuclear Technology / Volume 99 / Number 3 / September 1992 / Pages 343-350

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT92-A34718

A Computer Model for Predicting Transient Fission Gas Release from UO₂ Fuel

Ki-Seob Sim, Ho Chun Suk, Young Ku Yoon

Nuclear Technology / Volume 99 / Number 3 / September 1992 / Pages 351-365

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT92-A34719

The Advanced Fluid Dynamics Model Program: Scope and Accomplishment

William R. Bohl, Dirk Wilhelm

Nuclear Technology / Volume 99 / Number 3 / September 1992 / Pages 366-373

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT92-A34720

Thermohydraulic Model Experiments on the Transition from Forced to Natural Circulation for Pool-Type Fast Reactors

Helmut Hoffmann, Klaus Marten, Dietrich Weinberg, Hideki Kamide

Nuclear Technology / Volume 99 / Number 3 / September 1992 / Pages 374-385

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT92-A34721

Experiments on Convection Heat Transfer Along a Vertical Flat Plate Between Pools with Different Temperatures

Yoshiyuki Kataoka, Tohru Fukui, Shigeo Hatamiya, Toshitsugu Nakao, Masanori Naitoh, Isao Sumida

Nuclear Technology / Volume 99 / Number 3 / September 1992 / Pages 386-396

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT92-A34722