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Volume 194

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Number 1

Table of Contents

The Offshore Floating Nuclear Plant Concept

J. Buongiorno, J. Jurewicz, M. Golay, N. Todreas

Nuclear Technology / Volume 194 / Number 1 / April 2016 / Pages 1-14

Technical Paper / dx.doi.org/10.13182/NT15-49

Assembly Design of Pressurized Water Reactors with Fully Ceramic Microencapsulated Fuel

Rachel A. Shapiro, Massimiliano Fratoni

Nuclear Technology / Volume 194 / Number 1 / April 2016 / Pages 15-27

Technical Paper / dx.doi.org/10.13182/NT15-97

FiR 1 TRIGA Activity Inventories for Decommissioning Planning

Antti Räty, Petri Kotiluoto

Nuclear Technology / Volume 194 / Number 1 / April 2016 / Pages 28-38

Technical Paper / dx.doi.org/10.13182/NT15-86

Development of the APSRA⁺ Methodology for Passive System Reliability Analysis and Its Application to the Passive Isolation Condenser System of an Advanced Reactor

A. Chandrakar, A. K. Nayak, Vinod Gopika

Nuclear Technology / Volume 194 / Number 1 / April 2016 / Pages 39-60

Technical Paper / dx.doi.org/10.13182/NT15-80

Implementing Obliquely Inserted Control Rods Into RELAP5-3D/NESTLE Model for Atucha-2

R. G. Gonzalez, F. D'Auria, O. Mazzantini

Nuclear Technology / Volume 194 / Number 1 / April 2016 / Pages 61-72

Technical Paper / dx.doi.org/10.13182/NT14-155

Human Reliability Modeling of Radiotherapy Procedures by Bayesian Networks and Expert Opinion Elicitation

E. C. Gomes, J. P. Duarte, P. F. Frutuoso e Melo

Nuclear Technology / Volume 194 / Number 1 / April 2016 / Pages 73-96

Technical Paper / dx.doi.org/10.13182/NT15-29

Upgrade and Simulation of the Subcritical Assembly at Missouri University of Science and Technology

Lucas P. Tucker, Shoaib Usman, Ayodeji Alajo

Nuclear Technology / Volume 194 / Number 1 / April 2016 / Pages 97-110

Technical Paper / dx.doi.org/10.13182/NT15-67

X-Ray Residual Stress Measurement of Austenitic Stainless Steel Based on Fourier Analysis

Toshiyuki Miyazaki, Toshihiko Sasaki

Nuclear Technology / Volume 194 / Number 1 / April 2016 / Pages 111-116

Technical Note / dx.doi.org/10.13182/NT15-25

Evaluation of a Modified HPGe Preamplifier for High-Rate Spectroscopy Measurements in a Pulsed Photonuclear Environment

Xianfei Wen, Dante Nakazawa, Mat Kastner, Jason Pavlick, Haori Yang

Nuclear Technology / Volume 194 / Number 1 / April 2016 / Pages 117-125

Technical Note / dx.doi.org/10.13182/NT15-113

Number 2

Table of Contents
The Reemergence of the Thorium Fuel Cycle: A Special Issue of Nuclear Technology(Steven L. Krahn, Andrew Worrall)

Thorium Fuel Cycle Option Screening in the United States

Temitope A. Taiwo, Taek K. Kim, Roald A. Wigeland

Nuclear Technology / Volume 194 / Number 2 / May 2016 / Pages 127-135

Technical Note / dx.doi.org/10.13182/NT15-119

Natural Thorium Resources and Recovery: Options and Impacts

Timothy Ault, Bradley Van Gosen, Steven Krahn, Allen Croff

Nuclear Technology / Volume 194 / Number 2 / May 2016 / Pages 136-151

Technical Paper / dx.doi.org/10.13182/NT15-83

Liquid Fuel Molten Salt Reactors for Thorium Utilization

Jess C. Gehin, Jeffrey J. Powers

Nuclear Technology / Volume 194 / Number 2 / May 2016 / Pages 152-161

Technical Paper / dx.doi.org/10.13182/NT15-124

Analysis of Key Safety Metrics of Thorium Utilization in LWRs

Brian Ade, Andrew Worrall, Jeffrey Powers, Steve Bowman

Nuclear Technology / Volume 194 / Number 2 / May 2016 / Pages 162-177

Technical Paper / dx.doi.org/10.13182/NT15-100

Simulations of a Pressure-Tube Heavy Water Reactor Operating on Near-Breeding Thorium Cycles

Sourena Golesorkhi, Blair P. Bromley, Matthew H. Kaye

Nuclear Technology / Volume 194 / Number 2 / May 2016 / Pages 178-191

Technical Paper / dx.doi.org/10.13182/NT15-30

Multiregion Annular Heterogeneous Core Concepts for Plutonium-Thorium Fuels in Pressure-Tube Heavy Water Reactors

Blair P. Bromley

Nuclear Technology / Volume 194 / Number 2 / May 2016 / Pages 192-203

Technical Paper / dx.doi.org/10.13182/NT14-101

Steady State and Accident Transient Analysis Burning Weapons-Grade Plutonium in Thorium and Uranium with Silicon Carbide Cladding

Nathan Andrews, Koroush Shirvan, Edward E. Pilat, Mujid S. Kazimi

Nuclear Technology / Volume 194 / Number 2 / May 2016 / Pages 204-216

Technical Paper / dx.doi.org/10.13182/NT15-41

A Core Physics Study of Advanced Sodium-Cooled TRU Burners with Thorium- and Uranium-Based Metallic Fuels

Wuseung You, Ser Gi Hong

Nuclear Technology / Volume 194 / Number 2 / May 2016 / Pages 217-232

Technical Paper / dx.doi.org/10.13182/NT15-85

Thorium Fuel Cycles with Externally Driven Systems

Nicholas R. Brown, Jeffrey J. Powers, Michael Todosow, Massimiliano Fratoni, Hans Ludewig, Eva E. Sunny, Gilad Raitses, Arnold Aronson

Nuclear Technology / Volume 194 / Number 2 / May 2016 / Pages 233-251

Technical Paper / dx.doi.org/10.13182/NT15-40

ORNL Experience and Perspectives Related to Processing of Thorium and ²³³U for Nuclear Fuel

Allen G. Croff, Emory D. Collins, G. D. Del Cul, R. G. Wymer, Alan M. Krichinsky, B. B. Spencer, Brad D. Patton

Nuclear Technology / Volume 194 / Number 2 / May 2016 / Pages 252-270

Technical Paper / dx.doi.org/10.13182/NT15-59

Comparative Assessment of Thorium Fuel Cycle Radiotoxicity

Allen G. Croff, Steven L. Krahn

Nuclear Technology / Volume 194 / Number 2 / May 2016 / Pages 271-280

Technical Paper / dx.doi.org/10.13182/NT15-46

Safeguards Considerations for Thorium Fuel Cycles

Louise G. Worrall, Andrew Worrall, George F. Flanagan, Stephen Croft, Alan M. Krichinsky, Chris A. Pickett, Robert D. McElroy, Jr., Steven L. Cleveland, Donald N. Kovacic, J. Michael Whitaker, and Jessica L. White-Horton

Nuclear Technology / Volume 194 / Number 2 / May 2016 / Pages 281-293

Technical Paper / dx.doi.org/10.13182/NT15-103

Number 3

Understanding and Pathways to Avoid Major Fuel Failures and Radionuclide Releases in Fluoride Salt–Cooled High-Temperature Reactor Severe Accidents

C. W. Forsberg, J. D. Stempien, M. J. Minck, R. G. Ballinger

Nuclear Technology / Volume 194 / Number 3 / June 2016 / Pages 295-313

Technical Paper / dx.doi.org/10.13182/NT15-87

Partial Loading of Thorium-Plutonium Fuel in a Pressurized Water Reactor

M. Yousif Alhaj, Alya Badawi, Hanaa H. Abou-Gabal, Nader M. A. Mohamed

Nuclear Technology / Volume 194 / Number 3 / June 2016 / Pages 314-323

Technical Paper / dx.doi.org/10.13182/NT15-78

Neutronic Analysis of the PSBR Using a Burnup-Coupled MCNP Simulation with MURE

Dağıstan Şahin, Kenan Ünlü, Kostadin Ivanov

Nuclear Technology / Volume 194 / Number 3 / June 2016 / Pages 324-339

Technical Paper / dx.doi.org/10.13182/NT15-110

Impact of Rare Earth Recovery Fraction on Core Physics Parameters of the Korean SFR for TRU Transmutation

Sang Ji Kim, Pham Nhu Viet Ha, Jae Yong Lim

Nuclear Technology / Volume 194 / Number 3 / June 2016 / Pages 340-352

Technical Paper / dx.doi.org/10.13182/NT15-53

Adhesion Force Between a Silver Particle and Haynes 230: Role of Surface Conditions

Naphtali M. Mokgalapa, Tushar K. Ghosh, Robert V. Tompson, Sudarshan K. Loyalka

Nuclear Technology / Volume 194 / Number 3 / June 2016 / Pages 353-368

Technical Paper / dx.doi.org/10.13182/NT15-106

Gamma Radiation Thermal Stability of Two-Phase Mixtures of Nitric Acid with Degraded TBP in a Closed Vessel

E. R. Nazin, G. M. Zachinyaev, A. V. Rodin, E. V. Belova, G. P. Thorzhnitsky, B. F. Myasoedov

Nuclear Technology / Volume 194 / Number 3 / June 2016 / Pages 369-378

Technical Paper / dx.doi.org/10.13182/NT15-77

Filtering of Low-Level Radioactive Wastewater by Means of Vacuum Membrane Distillation

Xia Wen, Fuzhi Li, Xuan Zhao

Nuclear Technology / Volume 194 / Number 3 / June 2016 / Pages 379-386

Technical Paper / dx.doi.org/10.13182/NT15-74

Effects of Gas Rarefaction on Used Nuclear Fuel Cladding Temperatures During Vacuum Drying

M. Hadj-Nacer, T. Manzo, M. T. Ho, I. Graur, M. Greiner

Nuclear Technology / Volume 194 / Number 3 / June 2016 / Pages 387-399

Technical Paper / dx.doi.org/10.13182/NT15-82

MCNP Airport Investigation Room Design Based on Neutron-Gamma Technique

A. M. Reda

Nuclear Technology / Volume 194 / Number 3 / June 2016 / Pages 400-405

Technical Note / dx.doi.org/10.13182/NT15-92

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