ANS / Publications / Journals / Nuclear Technology

Core Design and Fuel Management Studies of a Thorium-Breeder Pebble Bed High-Temperature Reactor

Frank Wols, Jan Leen Kloosterman, Danny Lathouwers, Tim Van Der Hagen

Nuclear Technology / Volume 186 / Number 1 / April 2014 / Pages 1-16

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT13-14

High-Utilization Lattices for Thorium-Based Fuels in Heavy Water Reactors

Blair P. Bromley

Nuclear Technology / Volume 186 / Number 1 / April 2014 / Pages 17-32

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT13-86

A Feasibility Study of Load-Follow Operation Without Boron Adjustment for CPR1000

Li Wang, Yang Liu, Fuyu Zhao

Nuclear Technology / Volume 186 / Number 1 / April 2014 / Pages 33-44

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT13-15

Graphite Particle Adhesion to Hastelloy X: Measurements of the Adhesive Force with an Atomic Force Microscope

Naphtali M. Mokgalapa, Tushar K. Ghosh, Sudarshan K. Loyalka

Nuclear Technology / Volume 186 / Number 1 / April 2014 / Pages 45-59

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT13-9

A Neutronic Investigation of the Use of Fully Ceramic Microencapsulated Fuel for Pu/Np Burning in PWRs

Cole Gentry, Ivan Maldonado, Andrew Godfrey, Kurt Terrani, Jess Gehin, Jeffrey Powers

Nuclear Technology / Volume 186 / Number 1 / April 2014 / Pages 60-75

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT13-75

Stochastic Optimization for Nuclear Facility Deployment Scenarios Using VISION

Ross Hays, Paul Turinsky

Nuclear Technology / Volume 186 / Number 1 / April 2014 / Pages 76-89

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT13-68

Partial Defect Evaluation Methodology for Nuclear Safeguards Inspections of Used Nuclear Fuel Using the Digital Cherenkov Viewing Device

Sophie Grape, Staffan Jacobsson Svärd, Bo Lindberg

Nuclear Technology / Volume 186 / Number 1 / April 2014 / Pages 90-98

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT13-12

Modeling of Particulate Behavior in Pinhole Breaches

Andrew M. Casella, Sudarshan K. Loyalka, Brady D. Hanson

Nuclear Technology / Volume 186 / Number 1 / April 2014 / Pages 99-114

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT13-55

The Canary, the Ostrich, and the Black Swan: A Historical Perspective on our Understanding of BWR Severe Accidents and Their Mitigation

Sherrell R. Greene

Nuclear Technology / Volume 186 / Number 2 / May 2014 / Pages 115-138

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT13-44

NRC's Significance Determination Process: Current Status and Future Trends in Assessing Risks Attributed to External Events

Sunil D. Weerakkody

Nuclear Technology / Volume 186 / Number 2 / May 2014 / Pages 139-144

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT13-39

Insight From Fukushima Daiichi Unit 3 Investigations Using MELCOR

Kevin R. Robb, Matthew W. Francis, Larry J. Ott

Nuclear Technology / Volume 186 / Number 2 / May 2014 / Pages 145-160

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT13-43

MELCOR Simulations of the Severe Accident at the Fukushima Daiichi Unit 1 Reactor

Randall Gauntt, Donald Kalinich, Jeffrey Cardoni, Jesse Phillips

Nuclear Technology / Volume 186 / Number 2 / May 2014 / Pages 161-178

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT13-59

MELCOR Simulations of the Severe Accident at Fukushima Daiichi Unit 3

Jeffrey Cardoni, Randall Gauntt, Donald Kalinich, Jesse Phillips

Nuclear Technology / Volume 186 / Number 2 / May 2014 / Pages 179-197

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT13-41

A Reassessment of Low Probability Containment Failure Modes and Phenomena in a Long-Term Station Blackout

Acacia Brunett, Richard Denning, Tunc Aldemir

Nuclear Technology / Volume 186 / Number 2 / May 2014 / Pages 198-215

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT13-40

Estimation of the Depressurization Process of Fukushima Daiichi NPP Unit 1 with SAMPSON

Maolong Liu, Yuki Ishiwatari, Koji Okamoto

Nuclear Technology / Volume 186 / Number 2 / May 2014 / Pages 216-228

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT13-57

Material Effect in the Nuclear Fuel–Coolant Interaction: Analyses of Prototypic Melt Fragmentation and Solidification in the KROTOS Facility

Vaclav Tyrpekl, Pascal Piluso, Snejana Bakardjieva, Olivier Dugne

Nuclear Technology / Volume 186 / Number 2 / May 2014 / Pages 229-240

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT13-63

Early Phase Accident Progression Analysis of Fukushima Daiichi Unit 3 by the SAMPSON Code

Marco Pellegrini, Hiroaki Suzuki, Hideo Mizouchi, Masanori Naitoh

Nuclear Technology / Volume 186 / Number 2 / May 2014 / Pages 241-254

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT13-107

Analysis of Accident Progression with the SAMPSON Code in Fukushima Daiichi Nuclear Power Plant Unit 2

Hiroaki Suzuki, Masanori Naitoh, Atsuo Takahashi, Marco Pellegrini, Hidetoshi Okada

Nuclear Technology / Volume 186 / Number 2 / May 2014 / Pages 255-262

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT13-42

Update of the First TEPCO MAAP Accident Analysis of Units 1, 2, and 3 at Fukushima Daiichi Nuclear Power Station

Yasunori Yamanaka, Shinya Mizokami, Manabu Watanabe, Takeshi Honda

Nuclear Technology / Volume 186 / Number 2 / May 2014 / Pages 263-279

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT13-46

Successful Cold Shutdown of Onagawa: The Closest Nuclear Power Station to the March 11, 2011, Epicenter

Akiyoshi Obonai, Takao Watanabe, Kazuo Hirata

Nuclear Technology / Volume 186 / Number 2 / May 2014 / Pages 280-294

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT13-61

KAERI's Development of LWR Accident-Tolerant Fuel

Yang-Hyun Koo, Jae-Ho Yang, Jeong-Yong Park, Keon-Sik Kim, Hyun-Gil Kim, Dong-Joo Kim, Yang-Il Jung, Kun-Woo Song

Nuclear Technology / Volume 186 / Number 2 / May 2014 / Pages 295-304

Technical Note / Reactor Safety / dx.doi.org/10.13182/NT13-89

Assessment of MICROX-2 Code with New ENDF/B-VII Release 0 Master Libraries

Jia (Jason) Hou, Hangbok Choi, Kostadin Ivanov

Nuclear Technology / Volume 186 / Number 3 / June 2014 / Pages 305-316

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT12-137

Heterogeneous Cores for Implementation of Thorium-Based Fuels in Heavy Water Reactors

Blair P. Bromley, Bronwyn Hyland

Nuclear Technology / Volume 186 / Number 3 / June 2014 / Pages 317-339

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT13-85

A Study of the Containment Venting Strategy for the Fukushima Daiichi Accident

Yu-Huai Shih, Shih-Jen Wang, Kai-Cheng Chuang, Tzu-En Huang

Nuclear Technology / Volume 186 / Number 3 / June 2014 / Pages 340-352

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT12-145

Fuel Management of PWR Cores with Silicon Carbide Cladding

Jacob Dobisesky, Joshua Richard, Edward E. Pilat, Mujid S. Kazimi, David M. Carpenter

Nuclear Technology / Volume 186 / Number 3 / June 2014 / Pages 353-377

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT12-131

Uranium Startup Fast Reactors with Metal Fuel Using Once-Through Fuel Cycle

T. Fei, M. J. Driscoll, E. Shwageraus

Nuclear Technology / Volume 186 / Number 3 / June 2014 / Pages 378-389

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT13-21

A Core Design Study on the Fuel Displacement Options for an Effective Transition Between Breakeven and TRU Burning Sodium-Cooled Fast Reactors

Sang Ji Kim, Pham Nhu Viet Ha, Jae Yong Lim, Won Sik Yang

Nuclear Technology / Volume 186 / Number 3 / June 2014 / Pages 390-402

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT13-90

Quantitative NDA Measurements of Multiactinide Oxide Fuels

Braden Goddard, William Charlton, Paolo Peerani

Nuclear Technology / Volume 186 / Number 3 / June 2014 / Pages 403-414

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT13-18

Predicting Concrete Roadway Contribution to Gamma-Ray Background in Radiation Portal Monitor Systems

Christopher M. Ryan, Craig M. Marianno, William S. Charlton, Alexander A. Solodov, Ronald J. Livesay, Braden Goddard

Nuclear Technology / Volume 186 / Number 3 / June 2014 / Pages 415-426

Technical Paper / Radiation Transport and Protection / dx.doi.org/10.13182/NT13-98