American Nuclear Society
Home

Home / Publications / Journals / Nuclear Technology / Volume 146 / Number 2

Volume 146

Number 2

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