ANS / Publications / Journals / Nuclear Technology

Evaluation of Effective Prompt Neutron Lifetime for Pressurized Water Reactors

Heba K. Louis

Nuclear Technology / Volume 188 / Number 1 / October 2014 / Pages 1-7

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT13-120

Feasibility Study of a Soluble Boron–Free Small Modular Integral Pressurized Water Reactor

Justin Mart, Andrew Klein, Alexey Soldatov

Nuclear Technology / Volume 188 / Number 1 / October 2014 / Pages 8-19

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT13-135

A DFM/Fuzzy/ATHEANA Human Failure Analysis of a Digital Control System for a Pressurizer

J. M. O. Pinto, P. F. Frutuoso E Melo, P. L. C. Saldanha

Nuclear Technology / Volume 188 / Number 1 / October 2014 / Pages 20-33

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT13-48

Moderator Displacers for Reducing Coolant Void Reactivity in CANDU Reactors: A Scoping Study

Robert Farkas, Eleodor Nichita

Nuclear Technology / Volume 188 / Number 1 / October 2014 / Pages 34-44

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT13-128

Modeling and Analysis of a Heat Transport Transient Test Facility for Space Nuclear Systems

Adam R. Wheeler, Andrew C. Klein

Nuclear Technology / Volume 188 / Number 1 / October 2014 / Pages 45-62

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT13-100

Combining Insights from Probabilistic and Deterministic Safety Analyses in Option 4 from the IAEA Specific Safety Guide SSG-2

Milorad Dusic, Mark Dutton, Horst Glaeser, Joachim Herb, Javier Hortal, Rafael Mendizábal, Fernando Pelayo

Nuclear Technology / Volume 188 / Number 1 / October 2014 / Pages 63-77

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT13-16

A Three-Dimensional Computational Analysis of One-Way Fluid-Structure Coupling in Main Steam Isolation Valve

Li Wu, Jian Xiao, Hong Chen, Jia Li, Songzhi Jiang, Tongmin Wang

Nuclear Technology / Volume 188 / Number 1 / October 2014 / Pages 78-82

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT13-127

Measurement of Molten Chloride Salt Flow and Demonstration of Simulated Fission Product Removal Using a Zeolite Column Apparatus for Spent Salt Treatment in Pyroprocessing

Koichi Uozumi, Takatoshi Hijikata, Takeshi Tsukada, Tadafumi Koyama, Takayuki Terai, Akihiro Suzuki

Nuclear Technology / Volume 188 / Number 1 / October 2014 / Pages 83-96

Technical Paper / Reprocessing / dx.doi.org/10.13182/NT13-49

Simulations for Developing a Flag-Based Active Neutron Interrogation Method for Explosives Detection in Sea-Land Cargo Containers

Adrienne L. Lehnert, Kimberlee J. Kearfott

Nuclear Technology / Volume 188 / Number 1 / October 2014 / Pages 97-111

Technical Paper / Radiation Measurements and General Instrumentation / dx.doi.org/10.13182/NT11-125

Conceptual Design Enhancement for Prevention and Mitigation of Severe Accidents

Jin Ho Song

Nuclear Technology / Volume 188 / Number 2 / November 2014 / Pages 113-122

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT13-125

Impact of Accident-Tolerant Fuels and Claddings on the Overall Fuel Cycle: A Preliminary Systems Analysis

Gilles J. Youinou, R. Sonat Sen

Nuclear Technology / Volume 188 / Number 2 / November 2014 / Pages 123-138

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT14-22

Evaluation of Helical-Cruciform Fuel Rod Assemblies for High-Power-Density LWRs

T. M. Conboy, T. J. McKrell, M. S. Kazimi

Nuclear Technology / Volume 188 / Number 2 / November 2014 / Pages 139-153

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT13-104

Approach for Validating Actinide and Fission Product Compositions for Burnup Credit Criticality Safety Analyses

Georgeta Radulescu, Ian C. Gauld, Germina Ilas, John C. Wagner

Nuclear Technology / Volume 188 / Number 2 / November 2014 / Pages 154-171

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT13-154

Pyroelectric Energy Scavenging Techniques for Self-Powered Nuclear Reactor Wireless Sensor Networks

Scott R. Hunter, Nickolay V. Lavrik, Panos G. Datskos, Dwight Clayton

Nuclear Technology / Volume 188 / Number 2 / November 2014 / Pages 172-184

Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT13-136

Study on an Optimal Condition of Closed Chamber Distillation Equipment for Regeneration of LiCl-KCl Eutectic Salt Containing Rare Earth Phosphates

Hee-Chul Eun, Jung Hoon Choi, Yung Zun Cho, In Hak Cho, Hwan Seo Park, Geun Il Park

Nuclear Technology / Volume 188 / Number 2 / November 2014 / Pages 185-191

Technical Paper / Reprocessing / dx.doi.org/10.13182/NT13-146

Corrosion of 316L Stainless Steel Alloy and Hastelloy-N Superalloy in Molten Eutectic LiF-NaF-KF Salt and Interaction with Graphite

Robert S. Sellers, Wei-Jen Cheng, Brian C. Kelleher, Mark H. Anderson, Kumar Sridharan, Chaur-Jeng Wang, Todd R. Allen

Nuclear Technology / Volume 188 / Number 2 / November 2014 / Pages 192-199

Technical Paper / Materials for Nuclear Systems / dx.doi.org/10.13182/NT13-95

Extraction of Uranium from Seawater: Design and Testing of a Symbiotic System

Mathieu Picard, Camille Baelden, You Wu, Le Chang, Alexander H. Slocum

Nuclear Technology / Volume 188 / Number 2 / November 2014 / Pages 200-217

Technical Paper / Miscellaneous / dx.doi.org/10.13182/NT13-144

Verification and Validation of the ENDF/B-VII.1–Based Continuous-Energy Data Tables for MCNP6

Jeremy Lloyd Conlin, D. Kent Parsons, Steven J. Gardiner, Mark Gray, A. C. Kahler, M. Beth Lee, Morgan C. White

Nuclear Technology / Volume 188 / Number 2 / November 2014 / Pages 218-227

Technical Note / Fission Reactors / dx.doi.org/10.13182/NT13-153

Experimental Demonstration of a Heat Pipe–Stirling Engine Nuclear Reactor

David I. Poston, Patrick R. McClure, David D. Dixon, Marc A. Gibson, Lee S. Mason

Nuclear Technology / Volume 188 / Number 3 / December 2014 / Pages 229-237

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT13-71

Neutronics Studies of Uranium-Bearing Fully Ceramic Microencapsulated Fuel for Pressurized Water Reactors

Nathan Michael George, Ivan Maldonado, Kurt Terrani, Andrew Godfrey, Jess Gehin, Jeff Powers

Nuclear Technology / Volume 188 / Number 3 / December 2014 / Pages 238-251

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT14-3

Evaluation of Accumulated Fission Products in the Contaminated Water at the Fukushima Daiichi Nuclear Power Plant

Shunsuke Uchida, Masanori Naitoh, Hiroaki Suzuki, Hidetoshi Okada, Satoshi Konishi

Nuclear Technology / Volume 188 / Number 3 / December 2014 / Pages 252-265

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT13-152

An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses: Criticality (k_eff) Predictions

J. M. Scaglione, D. E. Mueller, J. C. Wagner

Nuclear Technology / Volume 188 / Number 3 / December 2014 / Pages 266-279

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT13-151

Plug Design for Deep Borehole Disposal of High-Level Nuclear Waste

E. A. Bates, A. Salazar, M. J. Driscoll, E. Baglietto, J. Buongiorno

Nuclear Technology / Volume 188 / Number 3 / December 2014 / Pages 280-291

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT12-166

Development of Natural Circulation Analytical Model in Super-COPD Code and Evaluation of Core Cooling Capability in Monju During a Station Blackout

Fumiaki Yamada, Yoshitaka Fukano, Hiroshi Nishi, Mamoru Konomura

Nuclear Technology / Volume 188 / Number 3 / December 2014 / Pages 292-321

Technical Note / Fission Reactors / dx.doi.org/10.13182/NT13-56

Optimized Flux Trap Dimensions in a Research Reactor Core

P. Savva, S. Chatzidakis, M. Varvayanni, A. Ikonomopoulos, N. Chrysanthopoulou, N. Catsaros, M. Antonopoulos-Domis

Nuclear Technology / Volume 188 / Number 3 / December 2014 / Pages 322-335

Technical Note / Fission Reactors / dx.doi.org/10.13182/NT13-108