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Volume 185

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Number 1

Analysis of Reactivity Insertion Accidents for the NIST Research Reactor Before and After Fuel Conversion

J. S. Baek, A. Cuadra, L.-Y. Cheng, A. L. Hanson, N. R. Brown, and D. J. Diamond

Nuclear Technology / Volume 185 / Number 1 / January 2014 / Pages 1-20

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT13-26

An Assessment of Corewide Coherency Effects in the Multichannel Modeling of the Initiating Phase of a Severe Accident in a Sodium Fast Reactor

M. Guyot, P. Gubernatis, C. Suteau, R. Le Tellier, and J. Lecerf

Nuclear Technology / Volume 185 / Number 1 / January 2014 / Pages 21-38

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT12-123

Depletion Reactivity Benchmarks—I: Experimental Benchmarks for Quantifying PWR Fuel Reactivity Depletion Uncertainty

K. S. Smith, T. Bahadir, R. Ferrer, D. B. Lancaster, and A. J. Machiels

Nuclear Technology / Volume 185 / Number 1 / January 2014 / Pages 39-56

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT13-31

Depletion Reactivity Benchmarks—II: Utilization in PWR Spent-Fuel Pool Criticality Analysis

D. B. Lancaster, K. S. Smith, and A. J. Machiels

Nuclear Technology / Volume 185 / Number 1 / January 2014 / Pages 57-70

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT13-28

Application of Augmented Reality to Nuclear Reactor Core Simulation for Fundamental Nuclear Engineering Education

Kosuke Tsujita, Tomohiro Endo, and Akio Yamamoto

Nuclear Technology / Volume 185 / Number 1 / January 2014 / Pages 71-84

Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT13-7

Installation of a New Neutron Beam Facility at the U.S. Geological Survey TRIGA Reactor

Aaron E. Craft and Jeffrey C. King

Nuclear Technology / Volume 185 / Number 1 / January 2014 / Pages 85-99

Technical Paper / Radiation Measurements and General Instrumentation / dx.doi.org/10.13182/NT13-4

Molten Salt Breeder Reactor Waste Management

Darryl D. Siemer

Nuclear Technology / Volume 185 / Number 1 / January 2014 / Pages 100-108

Technical Note / Reprocessing / dx.doi.org/10.13182/NT12-164

Number 2

Coupling of a Lumped Parameter and a Finite Difference Model for Estimation of a Reactivity-Induced Transient in a PWR with Annular Fuel Rods

J. P. Duarte, J. J. Rivero, P. F. Frutuoso E Melo, and A. C. M. Alvim

Nuclear Technology / Volume 185 / Number 2 / February 2014 / Pages 109-126

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT12-149

On the Use of Reduced-Moderation LWRs for Transuranic Isotope Burning in Thorium Fuel—I: Assembly Analysis

Benjamin A. Lindley, N. Zara Zainuddin, Paolo Ferroni, Andrew Hall, Fausto Franceschini, and Geoffrey T. Parks

Nuclear Technology / Volume 185 / Number 2 / February 2014 / Pages 127-146

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT13-53

On the Use of Reduced-Moderation LWRs for Transuranic Isotope Burning in Thorium Fuel—II: Core Analysis

Benjamin A. Lindley, N. Zara Zainuddin, Paolo Ferroni, Andrew Hall, Fausto Franceschini, and Geoffrey T. Parks

Nuclear Technology / Volume 185 / Number 2 / February 2014 / Pages 147-173

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT13-54

Uncertainty Analysis on Reactivity and Discharged Inventory Due to 235,238U, 239,240,241Pu, and Fission Products: Application to a Pressurized Water Reactor Fuel Assembly

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

Nuclear Technology / Volume 185 / Number 2 / February 2014 / Pages 174-191

Technical Paper / Fuel Cycle And Management / dx.doi.org/10.13182/NT12-154

Evaluating the Collective Radiation Dose to Workers from the U.S. Once-Through Nuclear Fuel Cycle

Steven L. Krahn, Allen G. Croff, Bethany L. Smith, James H. Clarke, Andrew G. Sowder, and Albert J. Machiels

Nuclear Technology / Volume 185 / Number 2 / February 2014 / Pages 192-207

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT13-64

A Heat Transfer Approach to the Calculation of Residual Power of Used Nuclear Fuel

Peter Schreiber, Pavol Tanuska, Robert Vrabel, and Pavel Vazan

Nuclear Technology / Volume 185 / Number 2 / February 2014 / Pages 208-215

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT12-138

Microfluidic-Based Robotic Sampling System for Radioactive Solutions

Jack D. Law, Julia L. Tripp, Tara E. Smith, John M. Svoboda, Veronica J. Rutledge, Troy G. Garn, and Larry Macaluso

Nuclear Technology / Volume 185 / Number 2 / February 2014 / Pages 216-225

Technical Paper / Reprocessing / dx.doi.org/10.13182/NT13-36

Number 3

Transient Analysis of Depressurized Loss-of-Forced-Circulation Accident Without Scram in High-Temperature Gas-Cooled Reactor

Hiroyuki Sato, Xing L. Yan, Yukio Tachibana, Kazuhiko Kunitomi, and Yukitaka Kato

Nuclear Technology / Volume 185 / Number 3 / March 2014 / Pages 227-238

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT13-97

Decoupling Control of Canadian Supercritical Water-Cooled Reactors

Peiwei Sun, Jin Jiang, and Kai Wang

Nuclear Technology / Volume 185 / Number 3 / March 2014 / Pages 239-258

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT12-130

A Dual System for Monitoring the Positions of Multiple Radioactive Tracer Pebbles in Scaled Pebble Bed Reactors

Zhijian Wang, Kyoung O. Lee, and Robin P. Gardner

Nuclear Technology / Volume 185 / Number 3 / March 2014 / Pages 259-269

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT13-13

Design Studies of a Low Sodium Void Reactivity Core Able to Accommodate Degraded TRU Fuel

Katsuyuki Kawashima, Kazuteru Sugino, Shigeo Ohki, and Tsutomu Okubo

Nuclear Technology / Volume 185 / Number 3 / March 2014 / Pages 270-280

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT13-38

Meeting the Needs of a Nuclear-Renewables Electrical Grid With a Fluoride-Salt–Cooled High-Temperature Reactor Coupled to a Nuclear Air-Brayton Combined-Cycle Power System

Charles Forsberg and Daniel Curtis

Nuclear Technology / Volume 185 / Number 3 / March 2014 / Pages 281-295

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT13-58

An Artificial Viscosity for the III-Posed One-Dimensional Incompressible Two-Fluid Model

William D. Fullmer, Sang Yong Lee, and Martin A. Lopez De Bertodano

Nuclear Technology / Volume 185 / Number 3 / March 2014 / Pages 296-308

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT13-66

Size Effect on Nuclear Gamma-Ray Energy Spectra Acquired By Different-Sized CeBr3, LaBr3:Ce, and Nai:Tl Gamma-Ray Detectors

Paul Guss, Michael Reed, Ding Yuan, Denis Beller, Matthew Cutler, Christopher Contreras, Sanjoy Mukhopadhyay, and Scott Wilde

Nuclear Technology / Volume 185 / Number 3 / March 2014 / Pages 309-321

Technical Paper / Radiation Transport and Protection / dx.doi.org/10.13182/NT13-2

Comparison of Radionuclide Releases from a Conceptual Geological Repository for RBMK-1500 and BWR Spent Nuclear Fuel

Povilas Poskas, Asta Narkuniene, Dalia Grigaliuniene, and Stefan Finsterle

Nuclear Technology / Volume 185 / Number 3 / March 2014 / Pages 322-335

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT13-52

 
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