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Volume 197

Number 3

Multiunit Accident Contributions to Quantitative Health Objectives: A Safety Goal Policy Analysis

Daniel W. Hudson, Mohammad Modarres

Nuclear Technology / Volume 197 / Number 3 / March 2017 / Pages 227-247

Technical Paper / dx.doi.org/10.1080/00295450.2016.1273714

Approaches to a Practical Systems Assessment for Safeguardability of Advanced Nuclear Fuel Cycles

R. A. Borrelli, Joonhang Ahn, Yongsoo Hwang

Nuclear Technology / Volume 197 / Number 3 / March 2017 / Pages 248-264

Technical Paper / dx.doi.org/10.1080/00295450.2016.1273713

BWR Control Rod Drift Analysis Capability in the U.S. NRC Core Simulator PATHS/PARCS

P. Yarsky, Y. Xu, A. Ward, N. Hudson, T. Downar

Nuclear Technology / Volume 197 / Number 3 / March 2017 / Pages 265-283

Technical Paper / dx.doi.org/10.1080/00295450.2016.1273707

Evaluation of the Pool Critical Assembly Benchmark with Explicitly Modeled Geometry Using MCNP6

Joel A. Kulesza, Roger L. Martz

Nuclear Technology / Volume 197 / Number 3 / March 2017 / Pages 284-295

Technical Paper / dx.doi.org/10.1080/00295450.2016.1273711

Security Analysis of Safety Critical and Control Systems: A Case Study of a Nuclear Power Plant System

Raj Kamal Kaur, Lalit Kumar Singh, Babita Pandey

Nuclear Technology / Volume 197 / Number 3 / March 2017 / Pages 296-307

Technical Paper / dx.doi.org/10.1080/00295450.2016.1273702

An Interactive Reverse-Engineering Cyclic Voltammetry for Uranium Electrochemical Studies in LiCl-KCl Eutectic Salt

Samaneh Rakhshan Pouri, Supathorn Phongikaroon

Nuclear Technology / Volume 197 / Number 3 / March 2017 / Pages 308-319

Technical Paper / dx.doi.org/10.1080/00295450.2016.1273730

Effect of Radiation on the Transmission Rate of Emission Intensity of Optical Fiber Cable Used in a Nuclear Material Facility

Daewoong Choi, Bo-Young Han, Se Hwan Park, Ho-dong Kim, Geun-il Park, Jeong-Hoe Ku

Nuclear Technology / Volume 197 / Number 3 / March 2017 / Pages 320-328

Technical Note / dx.doi.org/10.1080/00295450.2016.1273701

Real-Time In-Pile Acoustic Measurement Infrastructure at the Advanced Test Reactor

Vivek Agarwal, James A. Smith

Nuclear Technology / Volume 197 / Number 3 / March 2017 / Pages 329-333

NT Letter / dx.doi.org/10.1080/00295450.2016.1273704

 
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