ANS / Publications / Journals / Nuclear Technology

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