American Nuclear Society
Home

Home / Publications / Journals / Nuclear Technology / Volume 187 / Number 3

Volume 187

Number 3

Analysis of the Limiting Safety System Settings of a Fluoride Salt–Cooled High-Temperature Test Reactor

Yao Xiao, Lin-Wen Hu, Charles Forsberg, Suizheng Qiu, Guanghui Su, Kun Chen, Naxiu Wang

Nuclear Technology / Volume 187 / Number 3 / September 2014 / Pages 221-234

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT13-93

Modeling the Detection of Delayed Neutron Signatures in MCNP6 and Comparisons with Measurements of 233U, 235U, and 239Pu

M. T. Andrews, J. T. Goorley, E. C. Corcoran, D. G. Kelly

Nuclear Technology / Volume 187 / Number 3 / September 2014 / Pages 235-242

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT13-72

Application of an Improved Mechanical Shim Control Strategy for AP1000 Reactor

Pengfei Wang, Jiashuang Wan, Shoujun Yan, Yang Liu, Fuyu Zhao

Nuclear Technology / Volume 187 / Number 3 / September 2014 / Pages 243-259

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT13-111

Preliminary Economic Evaluation of Thorium-Based Fuels in PWRs

M. H. Du Toit, A. C. Cilliers

Nuclear Technology / Volume 187 / Number 3 / September 2014 / Pages 260-269

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT13-134

An Examination of CANDU Fuel Performance Margins Derived from a Statistical Assessment of Industrial Manufacturing Data

Travis A. Cunning, Paul Chan, Mahesh D. Pandey, Aniket Pant

Nuclear Technology / Volume 187 / Number 3 / September 2014 / Pages 270-281

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT13-126

Experimental Investigation of a Scaled Water-Cooled Reactor Cavity Cooling System

Rodolfo Vaghetto, Yassin A. Hassan

Nuclear Technology / Volume 187 / Number 3 / September 2014 / Pages 282-293

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT13-130

Thermal Modeling of High-Level Nuclear Waste Disposal in a Salt Repository

Dylan R. Harp, Philip H. Stauffer, Phoolendra K. Mishra, Daniel G. Levitt, Bruce A. Robinson

Nuclear Technology / Volume 187 / Number 3 / September 2014 / Pages 294-307

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT13-110

In-Core Flux Sensor Evaluations at the ATR Critical Facility

Troy Unruh, Benjamin Chase, Joy Rempe, David Nigg, George Imel, Jason Harris, Todd Sherman, Jean-François Villard

Nuclear Technology / Volume 187 / Number 3 / September 2014 / Pages 308-315

Technical Paper / Radiation Measurements and General Instrumentation / dx.doi.org/10.13182/NT13-122

Cesium Isotope Composition in Fukushima Daiichi Units After Boiling Water Reactor Accident

Masato Takahashi, Kenichi Yoshioka

Nuclear Technology / Volume 187 / Number 3 / September 2014 / Pages 316-327

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT13-114

Probability Correction Approach to Calibrate High-Purity Germanium Cylindrical Detectors Using Parallelepiped Sources

Sherif S. Nafee

Nuclear Technology / Volume 187 / Number 3 / September 2014 / Pages 328-336

Technical Note / Radiation Transport and Protection / dx.doi.org/10.13182/NT13-106

 
advertisement