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Volume 183

Number 1

Under-Sodium Endurance Experiment of Selector Valve in Failed-Fuel Detection and Location System of JSFR

Kosuke Aizawa, Kaoru Fujita, Shingo Hirata, Naoto Kasahara

Nuclear Technology / Volume 183 / Number 1 / July 2013 / Pages 1-12

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT13-A16988

Characteristics of Composite Silicon Carbide Fuel Cladding After Irradiation Under Simulated PWR Conditions

John D. Stempien, David M. Carpenter, Gordon Kohse, Mujid S. Kazimi

Nuclear Technology / Volume 183 / Number 1 / July 2013 / Pages 13-29

Technical Paper / Fuel Cycle and Management/Materials for Nuclear Systems / dx.doi.org/10.13182/NT12-86

Behavior of Transuranic Mixed-Oxide Fuel in a CANDU-900 Reactor

A. C. Morreale, M. R. Ball, D. R. Novog, J. C. Luxat

Nuclear Technology / Volume 183 / Number 1 / July 2013 / Pages 30-44

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT13-A16990

Entropy-Based Nuclear Fuel Cycle Sensitivities and Covariances

Anthony M. Scopatz, Erich A. Schneider, Jun Li, Man-Sung Yim

Nuclear Technology / Volume 183 / Number 1 / July 2013 / Pages 45-61

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT13-A16991

Verification and Validation of One-Dimensional Flow-Accelerated Corrosion Evaluation Code

Hiroaki Suzuki, Shunsuke Uchida, Masanori Naitoh, Hidetoshi Okada, Souji Koikari, Yukihiko Nagaya, Akira Nakamura, Seiichi Koshizuka, Derek H. Lister

Nuclear Technology / Volume 183 / Number 1 / July 2013 / Pages 62-74

Technical Paper / Thermal Hydraulics/Materials for Nuclear Systems / dx.doi.org/10.13182/NT13-A16992

Study on the Behavior of an Asymmetrically Heated Reactor Cavity Cooling System with Water in Single Phase

D. D. Lisowski, T. C. Haskin, A. Tokuhiro, M. H. Anderson, M. L. Corradini

Nuclear Technology / Volume 183 / Number 1 / July 2013 / Pages 75-87

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT13-A16993

Predictions of the Heat Transfer Coefficient by Correlations and Turbulence Models

Constantine P. Tzanos

Nuclear Technology / Volume 183 / Number 1 / July 2013 / Pages 88-100

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT13-A16994

Advantages of MCNPX-Based Lattice Tally over Mesh Tally in High-Speed Monte Carlo Dose Reconstruction for Proton Radiotherapy

Rui Zhang, Jonas D. Fontenot, Dragan Mirkovic, John S. Hendricks, Wayne D. Newhauser

Nuclear Technology / Volume 183 / Number 1 / July 2013 / Pages 101-106

Technical Paper / Radiation Transport and Protection / dx.doi.org/10.13182/NT13-A16995

Software Failure Probability Assessment by Bayesian Inference

Gee-Yong Park, Heung-Seop Eom, Seung Cheol Jang, Hyun Gook Kang

Nuclear Technology / Volume 183 / Number 1 / July 2013 / Pages 107-118

Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT13-A16996

Determination of Electrochemical Corrosion Potential Along the JMTR In-Pile Loop - I: Evaluation of ECP of Stainless Steel in High-Temperature Water as a Function of Oxidant Concentrations and Exposure Time

Shunsuke Uchida, Satoshi Hanawa, Yutaka Nishiyama, Takehiko Nakamura, Tomonori Satoh, Takashi Tsukada, Jan Kysela

Nuclear Technology / Volume 183 / Number 1 / July 2013 / Pages 119-135

Technical Paper / Materials for Nuclear Systems / dx.doi.org/10.13182/NT13-A16997

Determination of Electrochemical Corrosion Potential Along the JMTR In-Pile Loop - II: Validation of ECP Electrodes and the Extrapolation of Measured ECP Data

Satoshi Hanawa, Takehiko Nakamura, Shunsuke Uchida, Pavel Kus, Rudolf Vsolak, Jan Kysela, Masanori Sakai

Nuclear Technology / Volume 183 / Number 1 / July 2013 / Pages 136-148

Technical Paper / Reprocessing / dx.doi.org/10.13182/NT13-A16998

 

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