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Volume 188

Number 1

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

 
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