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Volume 146

Number 1

Simulation of the OECD Main-Steam-Line-Break Benchmark Exercise 3 Using the Coupled RELAP5/PANTHER Codes

Christophe R. Schneidesch, Jinzhao Zhang

Nuclear Technology / Volume 146 / Number 1 / April 2004 / Pages 1-14

Technical Paper / Reactor Safety

Consistent Comparison of the Codes RELAP5/PARCS and TRAC-M/PARCS for the OECD MSLB Coupled Code Benchmark

Tomasz Kozlowski, R. Matthew Miller, Thomas J. Downar, Douglas A. Barber, Han Gyu Joo

Nuclear Technology / Volume 146 / Number 1 / April 2004 / Pages 15-28

Technical Paper / Thermal Hydraulics

Methods and Results for the MSLB NEA Benchmark Using SIMTRAN and RELAP-5

José M. Aragonés, Carol Ahnert, Oscar Cabellos, Nuria García-Herranz, Vanessa Aragonés-Ahnert

Nuclear Technology / Volume 146 / Number 1 / April 2004 / Pages 29-40

Technical Paper / Thermal Hydraulics

Analysis of a Main-Steam-Line Break in Ascó NPP

Arántzazu Cuadra, José-Luis Gago, Francesc Reventós

Nuclear Technology / Volume 146 / Number 1 / April 2004 / Pages 41-48

Technical Paper / Thermal Hydraulics

Analytical Study on Fire and Explosion Accidents Assumed in HTGR Hydrogen Production System

Yoshitomo Inaba, Tetsuo Nishihara, Yoshikazu Nitta

Nuclear Technology / Volume 146 / Number 1 / April 2004 / Pages 49-57

Technical Paper / Reactor Safety

Calculations of the Neutron Flux Outside BWR 8 × 8 Spent-Fuel Assemblies and the Sensitivity to Fuel Pin Diversion

Peter Jansson, Ane Håkansson, Anders Bäcklin

Nuclear Technology / Volume 146 / Number 1 / April 2004 / Pages 58-64

Technical Paper / Fuel Cycle and Management

A Neural Network Model for the Tomographic Analysis of Irradiated Nuclear Fuel Rods

Teddy Craciunescu

Nuclear Technology / Volume 146 / Number 1 / April 2004 / Pages 65-71

Technical Paper / Fuel Cycle and Management

Isotopic Transmutations in Irradiated Beryllium and Their Implications on MARIA Reactor Operation

Krzysztof J. Andrzejewski, Teresa A. Kulikowska

Nuclear Technology / Volume 146 / Number 1 / April 2004 / Pages 72-82

Technical Paper / Radioactive Waste Management and Disposal

Counter-Permeation of Deuterium and Hydrogen Through INCONEL 600®

Tetsuaki Takeda, Jin Iwatsuki

Nuclear Technology / Volume 146 / Number 1 / April 2004 / Pages 83-95

Technical Paper / Materials for Nuclear Systems

 
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