ANS / Publications / Journals / Nuclear Technology

The Attractiveness of Materials in Advanced Nuclear Fuel Cycles for Various Proliferation and Theft Scenarios

Charles G. Bathke, Bartley B. Ebbinghaus, Brian A. Collins, Brad W. Sleaford, Kevin R. Hase, Martin Robel, Richard K. Wallace, Keith S. Bradley, John R. Ireland, Gordon D. Jarvinen, M. W. Johnson, Andrew W. Prichard, Brian W. Smith

Nuclear Technology / Volume 179 / Number 1 / July 2012 / Pages 5-30

Technical Paper / Special Issue on Safeguards / Materials for Nuclear Systems / dx.doi.org/10.13182/NT10-203

The Proliferation Resistance Debate and the Proliferation Resistance and Physical Protection Evaluation Methodology

Joseph F. Pilat

Nuclear Technology / Volume 179 / Number 1 / July 2012 / Pages 31-34

Technical Paper / Special Issue on Safeguards / Fuel Cycle and Management / dx.doi.org/10.13182/NT179-31

Proliferation Resistance and Physical Protection Evaluation Methodology: Objectives, Accomplishments, and Future Directions

Robert A. Bari

Nuclear Technology / Volume 179 / Number 1 / July 2012 / Pages 35-44

Technical Paper / Special Issue on Safeguards / Fuel Cycle and Management / dx.doi.org/10.13182/NT179-35

Elements of the Proliferation Resistance and Physical Protection Evaluation Methodology

Per F. Peterson

Nuclear Technology / Volume 179 / Number 1 / July 2012 / Pages 45-51

Technical Paper / Special Issue on Safeguards / Fuel Cycle and Management / dx.doi.org/10.13182/NT179-45

Implementation of the PR&PP Methodology: The Role of Formal Expert Elicitations

Joseph F. Pilat

Nuclear Technology / Volume 179 / Number 1 / July 2012 / Pages 52-60

Technical Paper / Special Issue on Safeguards / Fuel Cycle and Management / dx.doi.org/10.13182/NT179-52

Implications for Advanced Safeguards Derived from a Proliferation Resistance and Physical Protection Case Study for a Generation IV Nuclear Energy System

Brian D. Boyer, Heather H. Erpenbeck, Carolynn P. Scherer

Nuclear Technology / Volume 179 / Number 1 / July 2012 / Pages 61-69

Technical Paper / Special Issue on Safeguards / Fuel Cycle and Management / dx.doi.org/10.13182/NT179-61

A Qualitative Assessment of Diversion Scenarios for an Example Sodium Fast Reactor Using the Generation IV PR&PP Methodology

Michael D. Zentner, Garill A. Coles, Ike U. Therios

Nuclear Technology / Volume 179 / Number 1 / July 2012 / Pages 70-75

Technical Paper / Special Issue on Safeguards / Fuel Cycle and Management / dx.doi.org/10.13182/NT179-70

Applying the GIF PR&PP Methodology for a Qualitative Analysis of a Misuse Scenario in a Notional Generation IV Example Sodium Fast Reactor

Giacomo G. M. Cojazzi, Guido Renda, Jor Shan Choi, Jim Hassberger

Nuclear Technology / Volume 179 / Number 1 / July 2012 / Pages 76-90

Technical Paper / Special Issue on Safeguards / Fuel Cycle and Management / dx.doi.org/10.13182/NT179-76

Proliferation Resistance of a Hypothetical Sodium Fast Reactor Under an Assumed Breakout Scenario

Jeremy J. Whitlock, Naoko Inoue, Masao Senzaki, Dennis Bley, Ed Wonder

Nuclear Technology / Volume 179 / Number 1 / July 2012 / Pages 91-96

Technical Paper / Special Issue on Safeguards / Fuel Cycle and Management / dx.doi.org/10.13182/NT179-91

INPRO Studies of Proliferation Resistance for DUPIC Fuel Cycle

Yongdeok Lee, Jung Won Lee, Joo-Hwan Park

Nuclear Technology / Volume 179 / Number 1 / July 2012 / Pages 97-105

Technical Paper / Special Issue on Safeguards / Fuel Cycle and Management / dx.doi.org/10.13182/NT12-A14070

Interpretation and Use of the Results of Proliferation Resistance Studies

Michael D. Zentner, George Pomeroy, Robert A. Bari, Giacomo G. M. Cojazzi, Eckhart Haas, Thomas Killeen, P. Peterson, Jeremy J. Whitlock, Edward F. Wonder

Nuclear Technology / Volume 179 / Number 1 / July 2012 / Pages 106-111

Technical Paper / Special Issue on Safeguards / Fuel Cycle and Management / dx.doi.org/10.13182/NT12-A14071

Challenges to Integration of Safety and Reliability with Proliferation Resistance and Physical Protection for Generation IV Nuclear Energy Systems

H. Khalil, P. F. Peterson, R. Bari, G.-L. Fiorini, T. Leahy, R. Versluis

Nuclear Technology / Volume 179 / Number 1 / July 2012 / Pages 112-116

Technical Paper / Special Issue on Safeguards / Fuel Cycle and Management / dx.doi.org/10.13182/NT12-A14072

Strengthening the Nonproliferation Regime with Risk Acceptance Criteria

Edoardo Cavalieri d'Oro, Michael W. Golay

Nuclear Technology / Volume 179 / Number 1 / July 2012 / Pages 117-128

Technical Paper / Special Issue on Safeguards / Fuel Cycle and Management / dx.doi.org/10.13182/NT12-A14073

Informing Nuclear Energy Systems with Proliferation Risk

Edoardo Cavalieri d'Oro, Michael W. Golay

Nuclear Technology / Volume 179 / Number 1 / July 2012 / Pages 129-142

Technical Paper / Special Issue on Safeguards / Fuel Cycle and Management / dx.doi.org/10.13182/NT12-A14074

Integrating Safeguards and Security into Nuclear Facility Design

T. Bjornard, J. Morgan

Nuclear Technology / Volume 179 / Number 1 / July 2012 / Pages 143-149

Technical Paper / Special Issue on Safeguards / Fuel Cycle and Management / dx.doi.org/10.13182/NT12-A14075

Safety, Security, and Safeguards by Design: An Industrial Approach

Marius Stein, Massimo Morichi

Nuclear Technology / Volume 179 / Number 1 / July 2012 / Pages 150-155

Technical Paper / Special Issue on Safeguards / Fuel Cycle and Management / dx.doi.org/10.13182/NT12-A14076

Open Source Information Acquisition and Analysis in the International Atomic Energy Agency Department of Safeguards

Michael Barletta, Nicholas Zarimpas, Ryszard Zarucki

Nuclear Technology / Volume 179 / Number 1 / July 2012 / Pages 156-159

Technical Paper / Special Issue on Safeguards / Fuel Cycle and Management / dx.doi.org/10.13182/NT12-A14077

Benchmarked, Three-Dimensional Antineutrino Source Term Calculations of Light Water Reactors for Nonproliferation Applications

Elanchezhian Somasundaram, Todd S. Palmer, Alexey I. Soldatov

Nuclear Technology / Volume 179 / Number 1 / July 2012 / Pages 160-168

Technical Paper / Special Issue on Safeguards / Fuel Cycle and Management / dx.doi.org/10.13182/NT12-A14078

Generalized Perturbation Theory-Free Sensitivity Analysis for Eigenvalue Problems

Chris Kennedy, Cristian Rabiti, Hany Abdel-Khalik

Nuclear Technology / Volume 179 / Number 2 / August 2012 / Pages 169-179

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT179-169

Effects of Fuel Relocation for Transport Casks

Alan H. Wells, Albert J. Machiels

Nuclear Technology / Volume 179 / Number 2 / August 2012 / Pages 180-188

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT12-A14090

Fabrication of (U-Pu) Mixed-Oxide Fuel for Pressurized Heavy Water Reactors

J. P. Panakkal, M. Afzal, R. B. Bhatt, A. Prakash, A. K. Mishra, S. Kumar, H. S. Kamath

Nuclear Technology / Volume 179 / Number 2 / August 2012 / Pages 189-195

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT12-A14091

Determination of the Plutonium Mass and Curium Ratio of Spent Fuel Assemblies for Input Nuclear Material Accountancy of Pyroprocessing, and Analysis of Their Errors

Tae-Hoon Lee, Young-Soo Kim, Tae-Je Kwon, Hee-Sung Shin, Ho-Dong Kim

Nuclear Technology / Volume 179 / Number 2 / August 2012 / Pages 196-204

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT11-77

Water Chemistry in a Supercritical Water-Cooled Pressure Tube Reactor

D. Guzonas, F. Brosseau, P. Tremaine, J. Meesungnoen, J.-P. Jay-Gerin

Nuclear Technology / Volume 179 / Number 2 / August 2012 / Pages 205-219

Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT12-A14093

Pyrochemical Reprocessing Tests to Collect Uranium Metal from Simulated Spent Oxide Fuel

Yoshiharu Sakamura, Masaaki Akagi

Nuclear Technology / Volume 179 / Number 2 / August 2012 / Pages 220-233

Technical Paper / Reprocessing / dx.doi.org/10.13182/NT179-220

Theoretical Maximum Efficiencies of Optimized Slab and Spherical Betavoltaic Systems Utilizing Sulfur-35, Strontium-90, and Yttrium-90

Kyuhak Oh, Mark A. Prelas, Jason B. Rothenberger, Eric D. Lukosi, Jeho Jeong, Daniel E. Montenegro, Robert J. Schott, Charles L. Weaver, Denis A. Wisniewski

Nuclear Technology / Volume 179 / Number 2 / August 2012 / Pages 234-242

Technical Paper / Radioisotopes / dx.doi.org/10.13182/NT12-A14095

Theoretical Maximum Efficiency for a Linearly Graded Alphavoltaic Nuclear Battery

Kyuhak Oh, Mark A. Prelas, Eric D. Lukosi, Jason B. Rothenberger, Robert J. Schott, Charles L. Weaver, Daniel E. Montenegro, Denis A. Wisniewski

Nuclear Technology / Volume 179 / Number 2 / August 2012 / Pages 243-249

Technical Paper / Radioisotopes / dx.doi.org/10.13182/NT12-A14096

Criticality Evaluation for the Monju Restart Core

Taira Hazama, Akihiro Kitano, Y. Kishimoto

Nuclear Technology / Volume 179 / Number 2 / August 2012 / Pages 250-265

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT12-A14097

Control Rod Worth Evaluation for the Monju Restart Core

Kazuya Takano, Masahiro Fukushima, Taira Hazama, Takayuki Suzuki

Nuclear Technology / Volume 179 / Number 2 / August 2012 / Pages 266-285

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT12-A14098

Isothermal Temperature Coefficient Evaluation for the Monju Restart Core

Tetsuya Mouri, Shuhei Maruyama, Taira Hazama, Takayuki Suzuki

Nuclear Technology / Volume 179 / Number 2 / August 2012 / Pages 286-307

Technical Note / Fission Reactors / dx.doi.org/10.13182/NT12-A14099

Design Study to Increase Plutonium Conversion Ratio of HC-FLWR Core

Akifumi Yamaji, Yoshihiro Nakano, Sadao Uchikawa, Tsutomu Okubo

Nuclear Technology / Volume 179 / Number 3 / September 2012 / Pages 309-322

Technical Paper / Fission Reactors/Fuel Cycle and Management / dx.doi.org/10.13182/NT12-A14165

Propagation of ^235,236,238U and ²³⁹Pu Nuclear Data Uncertainties for a Typical PWR Fuel Element

D. Rochman, A. J. Koning, D. F. Da Cruz

Nuclear Technology / Volume 179 / Number 3 / September 2012 / Pages 323-338

Technical Paper / Fission Reactors/Fuel Cycle and Management / dx.doi.org/10.13182/NT11-61

Reactor Loose Part Damage Assessments on Steam Generator Tube Sheets

W. Cyrus Proctor, J. Michael Doster

Nuclear Technology / Volume 179 / Number 3 / September 2012 / Pages 339-359

Technical Paper / Fission Reactors/Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT12-A14167

Evaluation of JSFR Key Technologies

Yoshitaka Chikazawa, Kazumi Aoto, Hiroki Hayafune, Shoji Kotake, Yushi Ohno, Takaya Ito, Mikio Toda

Nuclear Technology / Volume 179 / Number 3 / September 2012 / Pages 360-373

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT179-360

An Examination of Simplification and Uncertainty on Material Attractiveness Evaluation for Proliferation Resistance Assessment

Steven E. Skutnik, Man-Sung Yim

Nuclear Technology / Volume 179 / Number 3 / September 2012 / Pages 374-381

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT12-A14169

Analysis of BR2 Loss-of-Flow Tests C and F

Constantine P. Tzanos, B. Dionne

Nuclear Technology / Volume 179 / Number 3 / September 2012 / Pages 382-391

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT12-A14170

An Algorithmic Approach for RELAP5/MOD3 Reactivity Insertion Analysis in Research Reactors

S. Chatzidakis, A. Ikonomopoulos, M. Alamaniotis

Nuclear Technology / Volume 179 / Number 3 / September 2012 / Pages 392-406

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT12-A14171

Studies on Separation of Minor Actinides from Lanthanides from High Level Waste by Extraction Chromatography Using 2,6-Bistriazinyl Pyridine

P. Deepika, K. N. Sabharwal, T. G. Srinivasan, P. R. Vasudeva Rao

Nuclear Technology / Volume 179 / Number 3 / September 2012 / Pages 407-416

Technical Paper / Reprocessing / dx.doi.org/10.13182/NT12-A14172

In-Situ Creep Testing Capability for the Advanced Test Reactor

Bong Goo Kim, Joy L. Rempe, Darrell L. Knudson, Keith G. Condie, Bulent H. Sencer

Nuclear Technology / Volume 179 / Number 3 / September 2012 / Pages 417-428

Technical Paper / Materials for Nuclear Systems / dx.doi.org/10.13182/NT12-A14173

Hemispherical Total Emissivity of Potential Structural Materials for Very High Temperature Reactor Systems: Haynes 230

Raymond K. Maynard, Naphtali M. Mokgalapa, Tushar K. Ghosh, Robert V. Tompson, Dabir S. Viswanath, Sudarshan K. Loyalka

Nuclear Technology / Volume 179 / Number 3 / September 2012 / Pages 429-438

Technical Paper / Materials for Nuclear Systems / dx.doi.org/10.13182/NT11-5