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Volume 161

Number 1 | Number 2 | Number 3

Number 1

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

Number 2

The Impact of Severe Accident Management Guidance on the Frequency of Containment Failure Modes of a Boiling Water Reactor

Kuan-Fu Chen, Ching-Hui Wu, Min Lee

Nuclear Technology / Volume 161 / Number 2 / February 2008 / Pages 81-97

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT08-A3915

Effect of the Surveillance Test Frequency of SDS1 on the Core Damage Probability

Sungwhan Cho, Jin Jiang

Nuclear Technology / Volume 161 / Number 2 / February 2008 / Pages 98-107

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT08-A3916

Core-Wide (In-Phase) Stability of Supercritical Water-Cooled Reactors - I: Sensitivity to Design and Operating Conditions

Jiyun Zhao, Pradip Saha, Mujid S. Kazimi

Nuclear Technology / Volume 161 / Number 2 / February 2008 / Pages 108-123

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT08-A3917

Core-Wide (In-Phase) Stability of Supercritical Water-Cooled Reactors - II: Comparison with Boiling Water Reactors

Jiyun Zhao, Pradip Saha, Mujid S. Kazimi

Nuclear Technology / Volume 161 / Number 2 / February 2008 / Pages 124-139

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT08-A3918

Impact of Spatial Heterogeneity of Source Term in Near-Surface Repository on Releases to Groundwater Pathway

Povilas Poskas, Raimondas Kilda, Valdas Ragaisis, Terry M. Sullivan

Nuclear Technology / Volume 161 / Number 2 / February 2008 / Pages 140-155

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT08-A3919

Long-Term Safety Assessment of a (Near-Surface) Short-Lived Radioactive Waste Repository in Lithuania

J. Mazeika, R. Petrosius, V. Jakimaviciute-Maseliene, D. Baltrunas, K. Mazeika, V. Remeikis, T. Sullivan

Nuclear Technology / Volume 161 / Number 2 / February 2008 / Pages 156-168

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT08-A3920

Corrosion Resistance of Amorphous Fe49.7Cr17.7Mn1.9Mo7.4W1.6B15.2C3.8Si2.4 Coating: A New Criticality Control Material

J. C. Farmer, J.-S. Choi, C.-K. Saw, R. H. Rebak, S. D. Day, T. Lian, P. D. Hailey, J. H. Payer, D. J. Branagan, L. F. Aprigliano

Nuclear Technology / Volume 161 / Number 2 / February 2008 / Pages 169-189

Technical Paper / Materials for Nuclear Systems / dx.doi.org/10.13182/NT08-A3921

Plutonium Release Fractions from Accidental Fires

Vladimir Kogan, Philip M. Schumacher

Nuclear Technology / Volume 161 / Number 2 / February 2008 / Pages 190-202

Technical Note / Miscellaneous / dx.doi.org/10.13182/NT08-A3922

Number 3

Development of Parameter-Identification Capability for MAAP4 Code

Chun-Sheng Chien, Shih-Jen Wang, Show-Chyuan Chiang

Nuclear Technology / Volume 161 / Number 3 / March 2008 / Pages 203-209

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT08-A3923

In-Vessel Retention of Molten Corium: Lessons Learned and Outstanding Issues

J. L. Rempe, K. Y. Suh, F. B. Cheung, S. B. Kim

Nuclear Technology / Volume 161 / Number 3 / March 2008 / Pages 210-267

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT08-A3924

Turbulence Model Assessment for Flow Across a Row of Confined Cylinders

Joshua Hodson, Robert Spall, Barton Smith

Nuclear Technology / Volume 161 / Number 3 / March 2008 / Pages 268-276

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT08-A3925

Performance Assessment of the Two-Phase Pump Degradation Model in the RELAP5-3D Transient Safety Analysis Code

Jeffrey W. Lane, L. E. Hochreiter, D. L. Aumiller, Jr., R. J. Kushner

Nuclear Technology / Volume 161 / Number 3 / March 2008 / Pages 277-285

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT08-A3926

A New Heat Transfer Correlation for Condensation in the Presence of Air and Its Implementation into RELAP5/MOD3.3

Fahri Aglar, Ali Tanrikut

Nuclear Technology / Volume 161 / Number 3 / March 2008 / Pages 286-298

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT08-A3927

Introduction of IDINHX, A New Heat Exchanger for Passive Decay Heat Removal

Yoon Sub Sim

Nuclear Technology / Volume 161 / Number 3 / March 2008 / Pages 299-314

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT08-A3928

Feasibility of Lead-Bismuth-Cooled Accelerator-Driven System for Minor-Actinide Transmutation

K. Tsujimoto, H. Oigawa, K. Kikuchi, Y. Kurata, M. Mizumoto, T. Sasa, S. Saito, K. Nishihara, M. Umeno, H. Takei

Nuclear Technology / Volume 161 / Number 3 / March 2008 / Pages 315-328

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT08-A3929

 
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