ANS / Publications / Journals / Nuclear Technology

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 / dx.doi.org/10.13182/NT04-A3482

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 / dx.doi.org/10.13182/NT04-A3483

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 / dx.doi.org/10.13182/NT04-A3484

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 / dx.doi.org/10.13182/NT04-A3485

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 / dx.doi.org/10.13182/NT04-A3486

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 / dx.doi.org/10.13182/NT04-A3487

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 / dx.doi.org/10.13182/NT04-A3488

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 / dx.doi.org/10.13182/NT04-A3489

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 / dx.doi.org/10.13182/NT04-A3490

Analysis of Seven NEPTUN-III (Tight-Lattice) Bottom-Flooding Experiments with RELAP5/MOD3.3/BETA

G. Th. Analytis

Nuclear Technology / Volume 146 / Number 2 / May 2004 / Pages 99-121

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT04-A3491

A Study of Boron and Temperature Mixing in the Downcomer and the Lower Part of a VVER Reactor Vessel

Yury A. Bezrukov, Sergey A. Logvinov, Vladimir N. Ul'yanovsky, Nikolay A. Strebnev

Nuclear Technology / Volume 146 / Number 2 / May 2004 / Pages 122-130

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT04-A3492

Development and Validation of ARKAS_cellule: An Advanced Core-Bowing Analysis Code for Fast Reactors

Hirokazu Ohta, Takeshi Yokoo, Masatoshi Nakagawa, Shinichiro Matsuyama

Nuclear Technology / Volume 146 / Number 2 / May 2004 / Pages 131-142

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT04-A3493

Criticality Data for Spherical ²³⁵U, ²³⁹Pu, and ²³⁷Np Systems Reflector-Moderated by Low Capturing-Moderator Materials

David J. Loaiza, William Stratton

Nuclear Technology / Volume 146 / Number 2 / May 2004 / Pages 143-154

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT04-A3494

Advanced MOX Core Design Study of Sodium-Cooled Reactors in Current Feasibility Study on Commercialized Fast Reactor Cycle Systems in Japan

Tomoyasu Mizuno, Hajime Niwa

Nuclear Technology / Volume 146 / Number 2 / May 2004 / Pages 155-163

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT04-4

Mechanical Analysis of High Power Internally Cooled Annular Fuel

Jiyun Zhao, Hee Cheon No, Mujid S. Kazimi

Nuclear Technology / Volume 146 / Number 2 / May 2004 / Pages 164-180

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT04-A3496

Decision Analysis and Its Application to the Frequency of Containment Integrated Leakage Rate Tests

George E. Apostolakis, John P. Koser, Gaku Sato

Nuclear Technology / Volume 146 / Number 2 / May 2004 / Pages 181-198

Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT04-A3497

Analysis of PWR RCS Injection Strategy During Severe Accident

Shih-Jen Wang, Kwang-Sheng Chiang, Show-Chyuan Chiang

Nuclear Technology / Volume 146 / Number 2 / May 2004 / Pages 199-205

Technical Note / Reactor Safety / dx.doi.org/10.13182/NT04-A3498

A Simple Kinetic Model for the Alpha Radiolysis of Water Sorbed on NpO₂

Alan S. Icenhour, Louis M. Toth, Robert M. Wham, R. R. Brunson

Nuclear Technology / Volume 146 / Number 2 / May 2004 / Pages 206-209

Technical Note / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT04-A3499

Effect of Replacing Helium with a Liquid Metal in the Fuel-Cladding Gap on Fission Gas Release

Doonyapong Wongsawaeng, Donald R. Olander

Nuclear Technology / Volume 146 / Number 3 / June 2004 / Pages 211-220

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT04-A3500

A Simplified Approach for Evaluation of the Burnup Potential of Alternative Fuels

Stella Maris Oggianu, Hee Cheon No, Mujid S. Kazimi

Nuclear Technology / Volume 146 / Number 3 / June 2004 / Pages 221-229

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT04-A3501

WISE: A New Fuel Cycle Concept Based on a Mobile Fuel Reactor

Igor Slessarev, G. Palmiotti, M. Salvatores, V. Berthou

Nuclear Technology / Volume 146 / Number 3 / June 2004 / Pages 230-243

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT04-A3502

Investigating the Nonlinear Dynamics of Natural-Circulation, Boiling Two-Phase Flows

Robert Zboray, Wilhelmus J. M. de Kruijf, Tim H. J. J. van der Hagen, Rizwan-uddin

Nuclear Technology / Volume 146 / Number 3 / June 2004 / Pages 244-256

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT04-A3503

IIST Passive Core Cooling on Pressurizer Top Break

Tay-Jian Liu, Chien-Hsiung Lee

Nuclear Technology / Volume 146 / Number 3 / June 2004 / Pages 257-266

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT04-A3504

Multilevel Methodology in Parallel Computing Environment for Evaluating BWR Safety Parameters

Jorge Solís, Maria N. Avramova, Kostadin N. Ivanov

Nuclear Technology / Volume 146 / Number 3 / June 2004 / Pages 267-278

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT04-A3505

Experimental Validation of CFD Analyses for Estimating the Transport Fraction of LOCA-Generated Insulation Debris to ECCS Sump Screens

Arup K. Maji, Bruce Letellier, Kyle W. Ross, Daseri V. Rao, Luke Bartlein

Nuclear Technology / Volume 146 / Number 3 / June 2004 / Pages 279-289

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT04-A3506

A Fuzzy Modeling Approach to Road Transport with Application to a Case of Spent Nuclear Fuel Transport

Marzio Marseguerra, Enrico Zio, Mauro Bianchi

Nuclear Technology / Volume 146 / Number 3 / June 2004 / Pages 290-302

Technical Paper / Criticality of Nuclear Materials / dx.doi.org/10.13182/NT04-A3507

Radiation Shielding Analysis for Direct Use of Spent Pressurized Water Reactor Fuel in CANDU Reactors (DUPIC)

Gyuhong Roh, Hangbok Choi

Nuclear Technology / Volume 146 / Number 3 / June 2004 / Pages 303-324

Technical Paper / Radiation Protection / dx.doi.org/10.13182/NT04-A3508

The Use of Molybdenum-Based Ceramic-Metal (CerMet) Fuel for the Actinide Management in LWRs

Klaas Bakker, Frodo C. Klaassen, Ronald P. C. Schram, Alfred Hogenbirk, Robin Klein Meulekamp, Arjan Bos, Hubert Rakhorst, Charles A. Mol

Nuclear Technology / Volume 146 / Number 3 / June 2004 / Pages 325-331

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT04-A3509