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Volume 184

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Number 1

A Stylized Three-Dimensional Pressurized Water Reactor Benchmark Problem with UO2 and MOX Fuel

Farzad Rahnema, Ryan Hon, Steven Douglass

Nuclear Technology / Volume 184 / Number 1 / October 2013 / Pages 1-28

Technical Paper / Reactor Physics / Pressurized Water Reactors / dx.doi.org/10.13182/NT11-124

Three-Dimensional Particle Transport Using Green's Functions in TRIPOLI-4 Monte Carlo Code: Application to PWR Neutron Fluence and Ex-Core Response Studies

S. Bourganel, O. Petit, C. M. Diop

Nuclear Technology / Volume 184 / Number 1 / October 2013 / Pages 29-41

Technical Paper / Neutron Transport and Shielding / dx.doi.org/10.13182/NT13-A19866

Improved Irradiation Performance of Uranium-Molybdenum/Aluminum Dispersion Fuel by Silicon Addition in Aluminum

Yeon Soo Kim, G. L. Hofman, A. B. Robinson, D. M. Wachs

Nuclear Technology / Volume 184 / Number 1 / October 2013 / Pages 42-53

Technical Paper / Fuel Design/Defects/Examination / Fuel Performance/Bu/Isotopes / dx.doi.org/10.13182/NT13-A19867

Rod-Inserted Sintering of Annular Pellets for Dual-Cooled Annular Fuel

Young Woo Rhee, Dong Joo Kim, Jong Hun Kim, Jae Ho Yang, Keon Sik Kim

Nuclear Technology / Volume 184 / Number 1 / October 2013 / Pages 54-62

Technical Paper / Fuel Design/Defects/Examination / Fuel Performance/Bu/Isotopes / dx.doi.org/10.13182/NT13-A19868

Development and Application of an Integrated Fuel Performance and Subchannel Model for Analysis of Sodium Fast Reactors

J. W. Fricano, J. Buongiorno

Nuclear Technology / Volume 184 / Number 1 / October 2013 / Pages 63-77

Technical Paper / Fuel Design/Defects/Examination / Materials for Nuclear Fuels / dx.doi.org/10.13182/NT13-A19869

Evolution of Charged Aerosols: Role of Charge on Coagulation

John F. Palsmeier, Sudarshan K. Loyalka

Nuclear Technology / Volume 184 / Number 1 / October 2013 / Pages 78-95

Technical Paper / Source Term Assessment / dx.doi.org/10.13182/NT184-78

Method for Analyzing Fission Gas Release in Fuel Rods Based on Gamma-Ray Measurements of Short-Lived Fission Products

Scott Holcombe, Staffan Jacobsson Svärd, Knut Eitrheim, Lars Hallstadius, Christofer Willman

Nuclear Technology / Volume 184 / Number 1 / October 2013 / Pages 96-106

Technical Paper / Source Term Assessment / Techniques for Measurements of Nuclear Data / Nondestructive Examination/Testing Methods / dx.doi.org/10.13182/NT13-A19871

Performance of Pyroprocess Equipment of Semi-Industrial Design and Material Balance in Repeated Engineering-Scale Fuel Cycle Tests Using Simulated Oxide/Metal Fuels

Masatoshi Iizuka, Kensuke Kinoshita, Yoshiharu Sakamura, Takanari Ogata, Tadafumi Koyama

Nuclear Technology / Volume 184 / Number 1 / October 2013 / Pages 107-120

Technical Paper / Pyrometallurgical Reprocessing / dx.doi.org/10.13182/NT13-A19872

Resource Requirements and Proliferation Risks Associated with Small Modular Reactors

Alexander Glaser, Laura Berzak Hopkins, M. V. Ramana

Nuclear Technology / Volume 184 / Number 1 / October 2013 / Pages 121-129

Technical Paper / Proliferation Issues/Nuclear Safeguards / dx.doi.org/10.13182/NT13-A19873

Number 2

Monte Carlo and Deterministic Neutronics Analyses of YALINA Thermal Facility and Comparison with Experimental Results

Alberto Talamo, Yousry Gohar, H. Kiyavitskaya, V. Bournos, Y. Fokov, C. Routkovskaya

Nuclear Technology / Volume 184 / Number 2 / November 2013 / Pages 131-147

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT13-A22310

Effective Reduction of Shutdown Dose Rate at Kuosheng Boiling Water Reactors Operating Under Hydrogen Water Chemistry

Tsung-Kuang Yeh, Mei-Ya Wang, Robin Wu

Nuclear Technology / Volume 184 / Number 2 / November 2013 / Pages 148-155

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT13-A22311

Parametric Core Analysis and Economic Feasibility of a Thorium Heavy Water Breeder Reactor

Taraknath Woddi, Kenneth N. Ricci

Nuclear Technology / Volume 184 / Number 2 / November 2013 / Pages 156-168

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT13-22

The Energy Multiplier Module: Advancing the Nuclear Fuel Cycle Through Technology Innovations

R. W. Schleicher, H. Choi, J. Rawls

Nuclear Technology / Volume 184 / Number 2 / November 2013 / Pages 169-180

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT13-A22313

Representative Source Terms and the Influence of Reactor Attributes on Functional Containment in Modular High-Temperature Gas-Cooled Reactors

D. A. Petti, R. R. Hobbins, P. Lowry, H. Gougar

Nuclear Technology / Volume 184 / Number 2 / November 2013 / Pages 181-197

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT184-181

Design, Construction, and Demonstration of the Colorado School of Mines Neutron Imaging Facility

Aaron E. Craft, Jeffrey C. King

Nuclear Technology / Volume 184 / Number 2 / November 2013 / Pages 198-209

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT13-A22315

The Consequences of a Sharp Temperature Change in the Fuel Pins of an Accelerator-Driven Subcritical System

R. Dagan, A. Jianu, G. Rimpault, A. Weisenburger, M. Schikorr

Nuclear Technology / Volume 184 / Number 2 / November 2013 / Pages 210-216

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT13-A22316

Experimental Validation of the DARWIN2.3 Package for Fuel Cycle Applications

L. San-Felice, R. Eschbach, P. Bourdot

Nuclear Technology / Volume 184 / Number 2 / November 2013 / Pages 217-232

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT12-121

Optimized Design of a PGNAA System for Cement Analysis Using Monte Carlo Simulations

J. B. Yang, X. G. Tuo, Z. Li, Y. Cheng, L. Wang, H. H. Wang, B. Cai, M. Z. Liu

Nuclear Technology / Volume 184 / Number 2 / November 2013 / Pages 233-238

Technical Paper / Radiation Transport and Protection / dx.doi.org/10.13182/NT13-A22318

A Notable Comparison of Computational Geometries in MCNP6 Calculations

Roger L. Martz, Kevin M. Marshall

Nuclear Technology / Volume 184 / Number 2 / November 2013 / Pages 239-248

Technical Paper / Radiation Transport and Protection / dx.doi.org/10.13182/NT13-A22319

The Issue of Accelerator Beam Trips for Efficient ADS Operation

G. Rimpault, Ph. Darde, F. Mellier, R. Dagan, M. Schikorr, A. Weisenburger, D. Maes, V. Sobolev, B. Arien, D. Lamberts, D. De Bruyn, A. C. Mueller, J. L. Biarrotte

Nuclear Technology / Volume 184 / Number 2 / November 2013 / Pages 249-260

Technical Paper / Accelerators / dx.doi.org/10.13182/NT12-75

Number 3

BWR-HD: An Optimized Boiling Water Reactor with High Power Density

Koroush Shirvan, Mujid Kazimi

Nuclear Technology / Volume 184 / Number 3 / December 2013 / Pages 261-273

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT13-A24984

Safety Analysis of BWR-HD: An Optimized Boiling Water Reactor with High Power Density

Koroush Shirvan, Mujid Kazimi

Nuclear Technology / Volume 184 / Number 3 / December 2013 / Pages 274-286

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT13-A24985

Stability Analysis of BWR-HD: An Optimized Boiling Water Reactor with High Power Density

Koroush Shirvan, Mujid Kazimi

Nuclear Technology / Volume 184 / Number 3 / December 2013 / Pages 287-296

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT13-A24986

Design of SPLC Architecture Used in Advanced Nuclear Safety System and Reliability Analysis Using Markov Model

Gwang Seop Son, Dong Hoon Kim, Choul Woong Son, Joon Kyo Kim, Jae Hyun Park

Nuclear Technology / Volume 184 / Number 3 / December 2013 / Pages 297-309

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT13-A24987

Operating Manipulator Arm by Robot Suit HAL for Remote In-Cell Equipment Maintenance

Akihiro Kitamura, Takashi Namekawa, Kousuke Hiramatsu, Yoshiyuki Sankai

Nuclear Technology / Volume 184 / Number 3 / December 2013 / Pages 310-319

Technical Paper / Robotic and Remote Systems / Human Factors / dx.doi.org/10.13182/NT13-A24988

Assessment of the Fingerprinting Method for the Verification of Spent Fuel in MACSTOR KN-400 CANDU Spent-Fuel Dry Storage

Nandan G. Chandregowda, Sunil S. Chirayath, William S. Charlton, Young Ham, Shiva Sitaraman, Gil Hoon Ahn

Nuclear Technology / Volume 184 / Number 3 / December 2013 / Pages 320-332

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT13-A24989

Uncertainty and Sensitivity Study in the Frame of TRACE Validation for Reflood Experiment

Wadim Jaeger, Victor Hugo Sanchez Espinoza

Nuclear Technology / Volume 184 / Number 3 / December 2013 / Pages 333-350

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT184-333

Quest for a Material for Sulfuric Acid Superheater/Decomposer for Sulfur-Iodine Thermochemical Cycle for Hydrogen Production

Michael S. Peck, Tushar K. Ghosh, Mark A. Prelas

Nuclear Technology / Volume 184 / Number 3 / December 2013 / Pages 351-363

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT13-A24991