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Volume 184

Number 2

Monte Carlo and Deterministic Neutronics Analyses of YALINA Thermal Facility and Comparison with Experimental Results

Alberto Talamo, Yousry Gohar, H. Kiyavitskaya, V. Bournos, Y. Fokov, C. Routkovskaya

Nuclear Technology / Volume 184 / Number 2 / November 2013 / Pages 131-147

Technical Paper / Fission Reactors

Effective Reduction of Shutdown Dose Rate at Kuosheng Boiling Water Reactors Operating Under Hydrogen Water Chemistry

Tsung-Kuang Yeh, Mei-Ya Wang, Robin Wu

Nuclear Technology / Volume 184 / Number 2 / November 2013 / Pages 148-155

Technical Paper / Fission Reactors

Parametric Core Analysis and Economic Feasibility of a Thorium Heavy Water Breeder Reactor

Taraknath Woddi, Kenneth N. Ricci

Nuclear Technology / Volume 184 / Number 2 / November 2013 / Pages 156-168

Technical Paper / Fission Reactors

The Energy Multiplier Module: Advancing the Nuclear Fuel Cycle Through Technology Innovations

R. W. Schleicher, H. Choi, J. Rawls

Nuclear Technology / Volume 184 / Number 2 / November 2013 / Pages 169-180

Technical Paper / Fission Reactors

Representative Source Terms and the Influence of Reactor Attributes on Functional Containment in Modular High-Temperature Gas-Cooled Reactors

D. A. Petti, R. R. Hobbins, P. Lowry, H. Gougar

Nuclear Technology / Volume 184 / Number 2 / November 2013 / Pages 181-197

Technical Paper / Fission Reactors

Design, Construction, and Demonstration of the Colorado School of Mines Neutron Imaging Facility

Aaron E. Craft, Jeffrey C. King

Nuclear Technology / Volume 184 / Number 2 / November 2013 / Pages 198-209

Technical Paper / Fission Reactors

The Consequences of a Sharp Temperature Change in the Fuel Pins of an Accelerator-Driven Subcritical System

R. Dagan, A. Jianu, G. Rimpault, A. Weisenburger, M. Schikorr

Nuclear Technology / Volume 184 / Number 2 / November 2013 / Pages 210-216

Technical Paper / Fuel Cycle and Management

Experimental Validation of the DARWIN2.3 Package for Fuel Cycle Applications

L. San-Felice, R. Eschbach, P. Bourdot

Nuclear Technology / Volume 184 / Number 2 / November 2013 / Pages 217-232

Technical Paper / Fuel Cycle and Management

Optimized Design of a PGNAA System for Cement Analysis Using Monte Carlo Simulations

J. B. Yang, X. G. Tuo, Z. Li, Y. Cheng, L. Wang, H. H. Wang, B. Cai, M. Z. Liu

Nuclear Technology / Volume 184 / Number 2 / November 2013 / Pages 233-238

Technical Paper / Radiation Transport and Protection

A Notable Comparison of Computational Geometries in MCNP6 Calculations

Roger L. Martz, Kevin M. Marshall

Nuclear Technology / Volume 184 / Number 2 / November 2013 / Pages 239-248

Technical Paper / Radiation Transport and Protection

The Issue of Accelerator Beam Trips for Efficient ADS Operation

G. Rimpault, Ph. Darde, F. Mellier, R. Dagan, M. Schikorr, A. Weisenburger, D. Maes, V. Sobolev, B. Arien, D. Lamberts, D. De Bruyn, A. C. Mueller, J. L. Biarrotte

Nuclear Technology / Volume 184 / Number 2 / November 2013 / Pages 249-260

Technical Paper / Accelerators

 
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