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Volume 192

Number 1 | Number 2 | Number 3

Number 1

Experimental and Analytical Assessment of Natural Circulation Interruption Phenomenon in the LSTF and PKL Test Facilities

A. Bousbia Salah, J. Vlassenbroeck, H. Austregesilo

Nuclear Technology / Volume 192 / Number 1 / October 2015 / Pages 1-10

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT14-51

Deformed Core Reactivity Evaluation with Mesh Projection–Based Method

M. Gentili, B. Fontaine, G. Rimpault

Nuclear Technology / Volume 192 / Number 1 / October 2015 / Pages 11-24

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT14-123

Comparison of Hydrogen Generation Rate Between CORA-13 Test and MELCOR Simulation: Clad Solid-Phase Oxidation Models Using Self-Developed Code MYCOAC

Jun Wang, Michael L. Corradini, Troy Haskin, Yapei Zhang, Qing Lu, Wenxi Tian, Guanghui Su, Suizheng Qiu

Nuclear Technology / Volume 192 / Number 1 / October 2015 / Pages 25-34

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT14-96

Study on Chemical Interaction of U3Si2 Dispersoid and Aluminum Matrix in Plate Fuel Elements and Its Influence on the Mechanical Properties

V. P. Sinha, D. Kohli, R. Rakesh, P. V. Thakar, A. Kumar

Nuclear Technology / Volume 192 / Number 1 / October 2015 / Pages 35-47

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT14-59

Advanced Nuclear Open Air-Brayton Cycles for Highly Efficient Power Conversion

Bahman Zohuri, Patrick J. McDaniel, Cassiano R. R. De Oliveira

Nuclear Technology / Volume 192 / Number 1 / October 2015 / Pages 48-60

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT14-42

Artificial Neural Networks and Chaos Dynamics for Radiation Signal Encryption

S. Chatzidakis, P. T. Forsberg, L. H. Tsoukalas

Nuclear Technology / Volume 192 / Number 1 / October 2015 / Pages 61-73

Technical Paper / Radiation Transport and Protection / dx.doi.org/10.13182/NT14-112

Methodology and Software for Gross Defect Detection of Spent Nuclear Fuel at the Atucha-I Reactor

Shivakumar Sitaraman, Young S. Ham, Narek Gharibyan, Orpet J. M. Peixoto, Gustavo Diaz

Nuclear Technology / Volume 192 / Number 1 / October 2015 / Pages 74-83

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT14-63

Calibration of the Conical Array for the Facility for Antiproton and Ion Research Using the Probability Correction Approach

Sherif S. Nafee

Nuclear Technology / Volume 192 / Number 1 / October 2015 / Pages 84-90

Technical Note / Radiation Transport and Protection / dx.doi.org/10.13182/NT14-89

Number 2

COSI6: A Tool for Nuclear Transition Scenario Studies and Application to SFR Deployment Scenarios with Minor Actinide Transmutation

C. Coquelet-Pascal, M. Tiphine, G. Krivtchik, D. Freynet, C. Cany, R. Eschbach, C. Chabert

Nuclear Technology / Volume 192 / Number 2 / November 2015 / Pages 91-110

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT15-20

Severe External Hazard on Hypothetical JSFR in 2010

Yoshitaka Chikazawa, Atsushi Katoh, Hiroyuki Hayafune, Yoshio Shimakawa, Yoshio Kamishima

Nuclear Technology / Volume 192 / Number 2 / November 2015 / Pages 111-124

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT14-151

Fuel Assembly Verification for Safe Operation of Nuclear Power Plants

Hitesh Rajput, Tanmoy Som, Soumitra Kar

Nuclear Technology / Volume 192 / Number 2 / November 2015 / Pages 125-132

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT14-154

Development of a SPECT System for Industrial Process Flow Measurement Using Diverging Collimators

Jang-Guen Park, Sung-Hee Jung, Jong Bum Kim, Jinho Moon, Chan Hyeong Kim

Nuclear Technology / Volume 192 / Number 2 / November 2015 / Pages 133-141

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT15-16

Dependence of Fire Time of Concern on Location of a One-Assembly Transport Package

Ketan Mittal, Ahti Suo-Anttila, Miles Greiner

Nuclear Technology / Volume 192 / Number 2 / November 2015 / Pages 142-154

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT14-156

Study on the Behavior of Radiolytically Produced Hydrogen in a High-Level Liquid Waste Tank of a Reprocessing Plant: Comparison Between Actual and Simulated Solutions

Hiroshi Kinuhata, Masahiko Yamamoto, Shigeo Taguchi, Naoki Surugaya, Soichi Sato, Takashi Kodama, Yoshikazu Tamauchi, Yuki Shibata, Kiyoshi Anzai, Shingo Matsuoka

Nuclear Technology / Volume 192 / Number 2 / November 2015 / Pages 155-159

Technical Paper / Reprocessing / dx.doi.org/10.13182/NT15-15

Uranous Nitrate Preparation by Catalytic Reduction: A Pilot Plant Facility

Avinash Sahu, Tessy Vincent

Nuclear Technology / Volume 192 / Number 2 / November 2015 / Pages 160-164

Technical Paper / Reprocessing / dx.doi.org/10.13182/NT15-9

Application of a One-Dimensional Transient Electrorefiner Model to Predict Partitioning of Plutonium from Curium in a Pyrochemical Spent Fuel Treatment Process

M. Gonzalez, L. Hansen, D. Rappleye, R. Cumberland, M. F. Simpson

Nuclear Technology / Volume 192 / Number 2 / November 2015 / Pages 165-171

Technical Paper / Reprocessing / dx.doi.org/10.13182/NT15-28

Maximum Likelihood Estimation of Neutron Source Location

Jian-Yu Zhu, Hao-Wei Dai, Wen-Xiong Xie

Nuclear Technology / Volume 192 / Number 2 / November 2015 / Pages 172-180

Technical Paper / Radiation Measurements and General Instrumentation / dx.doi.org/10.13182/NT14-115

Neutron Characteristics of Solid Targets in Accelerator-Driven System with 100-MeV Protons at Kyoto University Critical Assembly

Cheol Ho Pyeon, Hiroyuki Nakano, Masao Yamanaka, Takahiro Yagi, Tsuyoshi Misawa

Nuclear Technology / Volume 192 / Number 2 / November 2015 / Pages 181-190

Technical Paper / Accelerators / dx.doi.org/10.13182/NT14-111

Number 3

Optimal Shielding Design for Minimum Materials Cost or Mass

Robert D. Woolley

Nuclear Technology / Volume 192 / Number 3 / December 2015 / Pages 191-207

Technical Paper / Radiation Transport and Protection / dx.doi.org/10.13182/NT14-133

Radiation Protection Study for the First Korea Heavy-Ion Medical Accelerator Facility

Oyeon Kum, Seung Uk Heo, Sang Hyoun Choi, Yongkeun Song, Sung-Ho Cho

Nuclear Technology / Volume 192 / Number 3 / December 2015 / Pages 208-214

Technical Paper / Accelerators / dx.doi.org/10.13182/NT14-121

Design and Performance Test of Photosensitive Glass–Based Nonfocused X-Ray Antiscattering Grid by Using MCNP Simulation

Jun Woo Bae, Hee Reyoung Kim

Nuclear Technology / Volume 192 / Number 3 / December 2015 / Pages 215-221

Technical Paper / Radiation Measurements and General Instrumentation / dx.doi.org/10.13182/NT14-131

Experiment Design of Secondary Neutron and Charged-Particle Measurement with Stopping Targets Bombarded by 100 and 230 MeV/amu 4He Ions

Pi-En Tsai, Lawrence H. Heilbronn

Nuclear Technology / Volume 192 / Number 3 / December 2015 / Pages 222-231

Technical Paper / Radiation Transport and Protection / dx.doi.org/10.13182/NT14-130

Enhancements to the MCNP6 Background Source

Garrett E. McMath, Gregg W. McKinney

Nuclear Technology / Volume 192 / Number 3 / December 2015 / Pages 232-239

Technical Paper / Radiation Transport and Protection / dx.doi.org/10.13182/NT14-134

Computational Assessment of Naturally Occurring Neutron and Photon Background Radiation Produced by Extraterrestrial Sources

Thomas M. Miller, Wouter C. de Wet, Bruce W. Patton

Nuclear Technology / Volume 192 / Number 3 / December 2015 / Pages 240-249

Technical Paper / Radiation Measurements and General Instrumentation / dx.doi.org/10.13182/NT14-153

Testing the Delayed Gamma Capability in MCNP6

R. A. Weldon, Jr., M. L. Fensin, G. W. McKinney

Nuclear Technology / Volume 192 / Number 3 / December 2015 / Pages 250-258

Technical Paper / Radiation Transport and Protection / dx.doi.org/10.13182/NT14-127

Analog Neutron Transport for Nuclear Instrumentation Applications with the Monte Carlo Code TRIPOLI-4

O. Petit, E. Dumonteil

Nuclear Technology / Volume 192 / Number 3 / December 2015 / Pages 259-263

Technical Paper / Radiation Transport and Protection / dx.doi.org/10.13182/NT14-128

Enhanced Hybrid Diffusion-Transport Spatial Homogenization Method

Gabriel Kooreman, Farzad Rahnema

Nuclear Technology / Volume 192 / Number 3 / December 2015 / Pages 264-277

Technical Paper / Radiation Transport and Protection / dx.doi.org/10.13182/NT14-150

Activation Neutronics for a Swiss Pressurized Water Reactor

Manuel Pantelias, Benjamin Volmert

Nuclear Technology / Volume 192 / Number 3 / December 2015 / Pages 278-285

Technical Paper / Nuclear Plant Operations and Controls / dx.doi.org/10.13182/NT15-13

The Multi-Step CADIS Method for Shutdown Dose Rate Calculations and Uncertainty Propagation

Ahmad M. Ibrahim, Douglas E. Peplow, Robert E. Grove, Joshua L. Peterson, Seth R. Johnson

Nuclear Technology / Volume 192 / Number 3 / December 2015 / Pages 286-298

Technical Paper / Radiation Transport and Protection / dx.doi.org/10.13182/NT15-1

Radiation Mapping at JET and ITER Using Advanced Computational Acceleration Techniques and Tools

Jonathan Naish, Frances Fox, Zamir Ghani, Michael Loughlin, Lee Packer, Andrew Turner

Nuclear Technology / Volume 192 / Number 3 / December 2015 / Pages 299-307

Technical Paper / Accelerators / dx.doi.org/10.13182/NT14-132

Development of the Standalone Package for Enhanced Estimation of Dose Distribution for Space Radiation Applications

Wouter C. de Wet, Lawrence W. Townsend, X. George Xu, Whitney J. Smith

Nuclear Technology / Volume 192 / Number 3 / December 2015 / Pages 308-313

Technical Note / Radiation Biology / dx.doi.org/10.13182/NT15-21

 
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