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Volume 197

Number 1 | Number 2 | Number 3

Number 1

Experimental and Computational Forensics Characterization of Weapons-Grade Plutonium Produced in a Fast Reactor Neutron Environment

Mathew W. Swinney, Charles M. Folden III, Ronald J. Ellis, Sunil S. Chirayath

Nuclear Technology / Volume 197 / Number 1 / January 2017 / Pages 1-11

Technical Paper / dx.doi.org/10.13182/NT16-76

Sensitivity and Uncertainty Analysis of Plutonium and Cesium Isotopes in Modeling of BR3 Reactor Spent Fuel

Andrew Conant, Anna Erickson, Martin Robel, Brett Isselhardt

Nuclear Technology / Volume 197 / Number 1 / January 2017 / Pages 12-19

Technical Paper / dx.doi.org/10.13182/NT16-88

A Probabilistic Hazard Assessment Framework for Safety-Critical and Control Systems: A Case Study for a Nuclear Power Plant

Vinay Kumar, Lalit Singh, A. K. Tripathi

Nuclear Technology / Volume 197 / Number 1 / January 2017 / Pages 20-28

Technical Paper / dx.doi.org/10.13182/NT16-89

Core Design Studies of a Fast Reactor and Accelerator-Driven System for Two-Stage Fast Spectrum Fuel Cycle Option

Ching-Sheng Lin, Tongkyu Park, Won Sik Yang

Nuclear Technology / Volume 197 / Number 1 / January 2017 / Pages 29-46

Technical Paper / dx.doi.org/10.13182/NT16-90

Rod Internal Pressure Distribution and Uncertainty Analysis Using FRAPCON

Ryan N. Bratton, Matt A. Jessee, William A. Wieselquist, Kostadin N. Ivanov

Nuclear Technology / Volume 197 / Number 1 / January 2017 / Pages 47-63

Technical Paper / dx.doi.org/10.13182/NT16-75

Passive Reactivity Control of Nuclear Thermal Propulsion Reactors

Paolo F. Venneri, Michael Eades, Yonghee Kim

Nuclear Technology / Volume 197 / Number 1 / January 2017 / Pages 64-74

Technical Paper / dx.doi.org/10.13182/NT16-80

Study on a Low-Cost and Large-Scale Environmentally Adaptive Protocol Stack of Nuclear and Space Wireless Sensor Network Applications Under Gamma Radiation

Yu Liu, Michael Nishimura, Liqian Li, Karen Colins

Nuclear Technology / Volume 197 / Number 1 / January 2017 / Pages 75-87

Technical Paper / dx.doi.org/10.13182/NT16-97

Removal of Antimony over Nano Titania–Impregnated Epichlorohydrin-Crosslinked Chitosan Beads from a Typical Decontamination Formulation

Padala Abdul Nishad, Anupkumar Bhaskarapillai, Sankaralingam Velmurugan

Nuclear Technology / Volume 197 / Number 1 / January 2017 / Pages 88-98

Technical Paper / dx.doi.org/10.13182/NT16-77

Studies on Dissolution Behavior of the Surface Layer of Sodium-Exposed SS 316LN in Decontaminating Formulation Using PEMHS

C. Ramesh, N. Murugesan, V. Ganesan, N. Sivai Bharasi, M. G. Pujar, U. Kamachi Mudali

Nuclear Technology / Volume 197 / Number 1 / January 2017 / Pages 99-109

Technical Paper / dx.doi.org/10.13182/NT15-141

Reactivity Measurement Using the Area-Ratio Method in the BRAHMMA Subcritical System

Nirmal Kumar Ray, Tushar Roy, Shefali Bajpai, Tarun Patel, Yogesh Kashyap, Mayank Shukla, Amar Sinha

Nuclear Technology / Volume 197 / Number 1 / January 2017 / Pages 110-115

Technical Note / dx.doi.org/10.13182/NT16-71

Number 2

Tritium Control and Capture in Salt-Cooled Fission and Fusion Reactors: Status, Challenges, and Path Forward

Charles W. Forsberg, Stephen Lam, David M. Carpenter, Dennis G. Whyte, Raluca Scarlat, Cristian Contescu, Liu Wei, John Stempien, Edward Blandford

Nuclear Technology / Volume 197 / Number 2 / February 2017 / Pages 119-139

Critical Review / dx.doi.org/10.13182/NT16-101

Prediction of Countercurrent Flow Limitation and Its Uncertainty in Horizontal and Slightly Inclined Pipes

Michio Murase, Yoichi Utanohara, Takayoshi Kusunoki, Yasunori Yamamoto, Dirk Lucas, Akio Tomiyama

Nuclear Technology / Volume 197 / Number 2 / February 2017 / Pages 140-157

Technical Paper / dx.doi.org/10.13182/NT16-96

Experimental Investigation of Void Drift in Simulated Subchannels of a Natural-Circulation Pressure Tube–Type BWR

M. P. Sharma, A. K. Nayak

Nuclear Technology / Volume 197 / Number 2 / February 2017 / Pages 158-170

Technical Paper / dx.doi.org/10.13182/NT15-127

Modeling of Water Ingression Mechanism for Corium Cooling with MELCOR

Tuomo Sevón

Nuclear Technology / Volume 197 / Number 2 / February 2017 / Pages 171-179

Technical Paper / dx.doi.org/10.13182/NT16-108

Technical Basis for the Use of a Correlated Neutron Source in the Uranium Neutron Coincidence Collar

M. A. Root, H. O. Menlove, R. C. Lanza, C. D. Rael, K. A. Miller, J. B. Marlow

Nuclear Technology / Volume 197 / Number 2 / February 2017 / Pages 180-190

Technical Paper / dx.doi.org/10.13182/NT16-50

Thermal Conductivity Measurement of Granular UO2(NO3)2 · 6H2O

Gary M. Stange, Michael Corradini, Robert Swader, George Petry, Thomas R. Mackie, Kevin W. Eliceiri

Nuclear Technology / Volume 197 / Number 2 / February 2017 / Pages 191-200

Technical Paper / dx.doi.org/10.13182/NT16-107

Nuclear Radiation-Tolerant Wireless Transmitter Irradiation Test Results

Jorge V. Carvajal, Michael D. Heibel, Nicola G. Arlia, Andrew Bascom, Kenan Ünlü

Nuclear Technology / Volume 197 / Number 2 / February 2017 / Pages 201-208

Technical Paper / dx.doi.org/10.13182/NT16-92

Some Mathematical and Geophysical Considerations in Radioisotope Dating Applications

Robert B. Hayes

Nuclear Technology / Volume 197 / Number 2 / February 2017 / Pages 209-218

Technical Paper / dx.doi.org/10.13182/NT16-98

Removal of Cesium from Simulated Radioactive Wastewater Using a Novel Disc Tubular Reverse Osmosis System

Fei Jia, Jufeng Li, Jianlong Wang, Yuliang Sun

Nuclear Technology / Volume 197 / Number 2 / February 2017 / Pages 219-224

Technical Note / dx.doi.org/10.13182/NT16-6

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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