ANS / Publications / Journals / Nuclear Technology

Reliability Prediction of Passive Systems Based on Bivariate Probability Distributions

Luciano Burgazzi

Nuclear Technology / Volume 161 / Number 1 / January 2008 / Pages 1-7

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT08-A3908

Numerical Benchmarks for Very High-Temperature Reactors Based on the CNPS Critical Experiments

Hyung-Kook Joo, Temitope A. Taiwo, Won Sik Yang, Hussein S. Khalil

Nuclear Technology / Volume 161 / Number 1 / January 2008 / Pages 8-26

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT08-A3909

Dosimetric Management During a Criticality Accident

L. Lebaron-Jacobs, R. Fottorino, F. Barbry, P. Berard, F. Briot, P. Boisson, D. Cavadore, C. Challeton-de Vathaire, S. Distinguin, L. Exmelin, A. Flury-Herard, E. Gaillard-Lecanu, M. Gonin, J.-P. Le Goff, G. Lecoix, G. Lemaire, R. Medioni, M. H. Persico, Y. Racine, C. Riasse, E. Rongier, P. Voisin, A. Miele

Nuclear Technology / Volume 161 / Number 1 / January 2008 / Pages 27-34

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT08-A3910

French and United Kingdom Experience of High-Burnup Mixed-Oxide Fuel in Sodium-Cooled Fast Breeder Reactors

Philippe Martin, Michel Pelletier, Denis Every, Derek Buckthorpe

Nuclear Technology / Volume 161 / Number 1 / January 2008 / Pages 35-44

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT08-A3911

An Investigation of the Particle Size Responses for Various Fuel-Coolant Interactions in the TROI Experiments

I. K. Park, J. H. Kim, S. H. Hong, B. T. Min, S. W. Hong, J. H. Song, H. D. Kim

Nuclear Technology / Volume 161 / Number 1 / January 2008 / Pages 45-56

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT08-A3912

Lumped-Refined Multichannel Calculation Scheme for a High-Fidelity Thermal-Hydraulic Analysis by a Neutronics Code Coupling

Jin-Young Cho, Jae-Seung Song, Chung-Chan Lee, Sung-Quun Zee, Jae-Il Lee, Kil-Sup Um

Nuclear Technology / Volume 161 / Number 1 / January 2008 / Pages 57-68

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT08-A3913

Numerical Computation of Heat Transfer Enhancement of a PWR Rod Bundle with Mixing Vane Spacers

Wang-Kee In, Tae-Hyun Chun, Chang-Hwan Shin, Dong-Seok Oh

Nuclear Technology / Volume 161 / Number 1 / January 2008 / Pages 69-79

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT08-A3914