ANS / Publications / Journals / Nuclear Technology

Variation of Burnable Neutron Absorbers in a Heavy Water–Moderated Fuel Lattice: A Potential to Improve CANDU Reactor Operating Margins

Paul K. Chan, Stephane Paquette, Hugues W. Bonin

Nuclear Technology / Volume 191 / Number 1 / July 2015 / Pages 1-14

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT14-67

Study on Heat Removal Capacity of PCCS of Advanced Passive PWR During Severe Accidents

Lili Tong, Jie Zou, Jun Tao, Xuewu Cao

Nuclear Technology / Volume 191 / Number 1 / July 2015 / Pages 15-26

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT14-93

DART Analysis of Irradiation Behavior of U-Mo/Al Dispersion Fuels

Bei Ye, Jeff Rest, Yeon Soo Kim, Gerard Hofman, Benoit Dionne

Nuclear Technology / Volume 191 / Number 1 / July 2015 / Pages 27-40

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT14-56

Intelligent Analysis of Low-Count Scintillation Spectra Using Support Vector Regression and Fuzzy Logic

Miltiadis Alamaniotis, Sangkyu Lee, Tatjana Jevremovic

Nuclear Technology / Volume 191 / Number 1 / July 2015 / Pages 41-57

Technical Paper / Radiation Transport and Protection / dx.doi.org/10.13182/NT14-75

Corrosion Behavior of Zirconium, Titanium, and Their Alloys in Simulated Dissolver Solution of Fast Breeder Reactor Spent Nuclear Fuel Using Zircaloy-4 Mock-Up Dissolver Vessel

J. Jayaraj, K. Thyagarajan, C. Mallika, U. Kamachi Mudali

Nuclear Technology / Volume 191 / Number 1 / July 2015 / Pages 58-70

Technical Paper / Reprocessing / dx.doi.org/10.13182/NT14-90

Particle Production by Rotational Abrasion Between Graphite Spheres

Raymond S. Troy, Robert V. Tompson, Tushar K. Ghosh, Sudarshan K. Loyalka

Nuclear Technology / Volume 191 / Number 1 / July 2015 / Pages 71-91

Technical Note / Fission Reactors / dx.doi.org/10.13182/NT14-109

Design and Laboratory Evaluation of Future Elongation and Diameter Measurements at the Advanced Test Reactor

K. L. Davis, D. L. Knudson, J. L. Rempe, J. C. Crepeau, S. Solstad

Nuclear Technology / Volume 191 / Number 1 / July 2015 / Pages 92-105

Technical Note / Materials for Nuclear Systems / dx.doi.org/10.13182/NT14-60

Degradation of Nylon 6,6 Fire-Suppression Casing from Plutonium Glove Boxes Under Alpha and Neutron Irradiation

D. W. Millsap, M. E. Cournoyer, S. Landsberger, J. Tesmer, Y. Wang

Nuclear Technology / Volume 191 / Number 1 / July 2015 / Pages 106-112

Technical Note / Materials for Nuclear Systems / dx.doi.org/10.13182/NT14-47

Spent Nuclear Fuel and Graphite Management for Salt-Cooled Reactors: Storage, Safeguards, and Repository Disposal

Charles Forsberg, Per F. Peterson

Nuclear Technology / Volume 191 / Number 2 / August 2015 / Pages 113-121

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT14-88

An Investigation on Size Distribution and Physical Characteristics of Debris in TROI FCI Tests

Seong-Wan Hong, Beong-Tae Min, Seong-Ho Hong

Nuclear Technology / Volume 191 / Number 2 / August 2015 / Pages 122-135

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT14-84

MARS-KS Code and Sensitivity Analysis of a Pressure Wave Propagation Test Performed in the PMK-2 Test Facility

Xin-Guo Yu, Ki-Yong Choi, Chul-Hwa Song, Istvan Trosztel, Ivan Toth, Gyorgy Ezsol

Nuclear Technology / Volume 191 / Number 2 / August 2015 / Pages 136-150

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT14-55

Innovative Control Strategy for Fast Runback Operational Transient Applied to SMRs

Roberto Ponciroli, Stefano Passerini, Richard B. Vilim

Nuclear Technology / Volume 191 / Number 2 / August 2015 / Pages 151-166

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT14-68

Development of High-Temperature Transport System for LiCl-KCl Molten Salt in Pyroprocessing

Sung Ho Lee, Geun Il Park, Sung Bin Park

Nuclear Technology / Volume 191 / Number 2 / August 2015 / Pages 167-173

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT14-87

Monte Carlo Perturbation Analysis of Isothermal Temperature Reactivity Coefficient in Kyoto University Critical Assembly

Byoung Kyu Jeon, Cheol Ho Pyeon, Hyung Jin Shim

Nuclear Technology / Volume 191 / Number 2 / August 2015 / Pages 174-184

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT14-83

An Assessment of the Virtual Mass Force in RELAP5/MOD3.3 for the Bubbly Flow Regime

William D. Fullmer, Martin A. Lopez De Bertodano

Nuclear Technology / Volume 191 / Number 2 / August 2015 / Pages 185-192

Technical Note / Fission Reactors / dx.doi.org/10.13182/NT14-110

Performance of the Explicit Euler and Predictor-Corrector–Based Coupling Schemes in Monte Carlo Burnup Calculations of Fast Reactors

Ignas Mickus, Jan Dufek, Kaur Tuttelberg

Nuclear Technology / Volume 191 / Number 2 / August 2015 / Pages 193-198

Technical Note / Reprocessing / dx.doi.org/10.13182/NT14-48

The Use of Flashing Drums and Microchannel Heat Exchangers to Generate Steam in Large Integral Light Water Reactors

Matthew J Memmott, Annalisa Manera

Nuclear Technology / Volume 191 / Number 3 / September 2015 / Pages 199-212

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT14-103

Analytical Study on the Effective Thermal Conductivity of VHTR Fuel Block Geometry with Multiple Cylindrical Holes

Dong-Ho Shin, Su-Jong Yoon, Nam-Il Tak, Goon-Cherl Park, Hyoung-Kyu Cho

Nuclear Technology / Volume 191 / Number 3 / September 2015 / Pages 213-222

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT14-102

Interactive Simulation and Visualization of In-Reactor and Under-Sodium Viewing Operations

Young S. Park, Xiaorui Zhao, Pawel Dworzanski, Zachary T. Gima, Richard B. Vilim

Nuclear Technology / Volume 191 / Number 3 / September 2015 / Pages 223-233

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT14-108

TRIPOLI-4 Simulation of Core Physics Parameters for Two 3600-MW(thermal) Sodium-Cooled Fast Reactors

Yi-Kang Lee, Emeric Brun, Xavier Alexandre

Nuclear Technology / Volume 191 / Number 3 / September 2015 / Pages 234-245

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT14-85

Preliminary Evaluation of Recriticality Potential for ESFR Core and Conditions for Its Elimination

Franco Polidoro, Michael Flad, Werner Maschek

Nuclear Technology / Volume 191 / Number 3 / September 2015 / Pages 246-253

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT14-97

Designing for Inherent Control in Liquid-Metal Advanced Small Modular Reactors

Stefano Passerini, Richard B. Vilim

Nuclear Technology / Volume 191 / Number 3 / September 2015 / Pages 254-267

Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT14-99

Fuel Performance Analysis of a (ThU)O₂-Fueled, Reduced Moderation Boiling Water Reactor

Alexander J. Mieloszyk, Mujid S. Kazimi

Nuclear Technology / Volume 191 / Number 3 / September 2015 / Pages 268-281

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT14-104

Trade-Off Studies for the Fuel-Self-Sustaining RBWR-Th Core

Phillip M. Gorman, Jasmina L. Vujic, Ehud Greenspan

Nuclear Technology / Volume 191 / Number 3 / September 2015 / Pages 282-294

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT14-106