ANS / Publications / Journals / Nuclear Technology

Progress of the DUPIC Fuel Compatibility Analysis - IV: Fuel Performance

Hangbok Choi, Ho Jin Ryu, Gyuhong Roh, Chang Joon Jeong, Chang Je Park, Kee Chan Song, Jung Won Lee, Myung Seung Yang

Nuclear Technology / Volume 157 / Number 1 / January 2007 / Pages 1-17

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT07-A3798

Comparative Transient Analysis of Critical and Subcritical 80-MW Pb-Bi Eutectic-Cooled Reactor Systems

K. Mikityuk, P. Coddington, S. Pelloni, E. Bubelis, R. Chawla

Nuclear Technology / Volume 157 / Number 1 / January 2007 / Pages 18-36

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT07-A3799

Zirconium Matrix Cermet for a Mixed Uranium-Thorium Oxide Fuel in an SBWR

Sean M. McDeavitt, Yunlin Xu, Thomas J. Downar, Alvin A. Solomon

Nuclear Technology / Volume 157 / Number 1 / January 2007 / Pages 37-52

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT07-A3800

Improvement of Fuel Performance Code COSMOS with Recent In-Pile Data for MOX and UO₂ Fuels

Byung-Ho Lee, Yang-Hyun Koo, Je-Yong Oh, Jin-Sik Cheon, Dong-Seong Sohn

Nuclear Technology / Volume 157 / Number 1 / January 2007 / Pages 53-64

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT07-A3801

Integrator Circuit as an Analogy for Convection

S. Usman, S. Abdallah, M. Hawwari, M. Scarangella, L. Shoaib

Nuclear Technology / Volume 157 / Number 1 / January 2007 / Pages 65-73

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT07-A3802

Water Adsorption Isotherms for Charged and Uncharged Cesium Iodide Aerosol Particles

Charles A. Riggs, Robert V. Tompson, Tushar K. Ghosh, Sudarshan K. Loyalka, Dabir S. Viswanath

Nuclear Technology / Volume 157 / Number 1 / January 2007 / Pages 74-86

Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT07-A3803

Environmental Impact of Yucca Mountain Repository in the Case of Canister Failure

Joonhong Ahn

Nuclear Technology / Volume 157 / Number 1 / January 2007 / Pages 87-105

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT07-A3804

Dead-Time Correction for Nonparalyzing Detectors When Measuring Short-Lived Nuclides

Andrija S. Radovic, Shoaib Usman

Nuclear Technology / Volume 157 / Number 1 / January 2007 / Pages 106-109

Technical Paper / Radiation Measurements and Instrumentation / dx.doi.org/10.13182/NT07-A3805

Research and Development on System Integration Technology for Connection of Hydrogen Production System to an HTGR

Yoshiyuki Inagaki, Hirofumi Ohashi, Yoshitomo Inaba, Hiroyuki Sato, Tetsuo Nishihara, Tetsuaki Takeda, Koji Hayashi, Masuro Ogawa

Nuclear Technology / Volume 157 / Number 2 / February 2007 / Pages 111-119

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT07-A3806

A Compact Loop-Type Fast Reactor Without Refueling for a Remote Area Power Source

Yoshitaka Chikazawa, Yasushi Okano, Mamoru Konomura, Naoki Sawa, Yoshio Shimakawa, Toshihiko Tanaka

Nuclear Technology / Volume 157 / Number 2 / February 2007 / Pages 120-131

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT07-A3807

Benchmark Study on Fuel Bundle Degradation in the Phebus FPT3 Test Using the Severe Accident Codes ATHLET-CD, ICARE2, and MELCOR

Bela Toth, Klaus Mueller, Jon Birchley, Hozumi Wada, Claude Jamond, Klaus Trambauer

Nuclear Technology / Volume 157 / Number 2 / February 2007 / Pages 132-142

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT07-A3808

Proliferation Resistance Assessment Methodology for Nuclear Fuel Cycles

William S. Charlton, Ryan F. LeBouf, Claudio Gariazzo, D. Grant Ford, Carl Beard, Sheldon Landsberger, Michael Whitaker

Nuclear Technology / Volume 157 / Number 2 / February 2007 / Pages 143-156

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT07-A3809

Fertile-Free Fuels in Pressurized Water Reactors: Design Challenges and Solutions

E. Fridman, E. Shwageraus, A. Galperin

Nuclear Technology / Volume 157 / Number 2 / February 2007 / Pages 157-176

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT07-A3810

Validation of Coupled Thermal-Hydraulic and Neutronics Codes for Safety Analysis by International Cooperations

Kostadin Ivanov, Enrico Sartori, E. Royer, S. Langenbuch, K. Velkov

Nuclear Technology / Volume 157 / Number 2 / February 2007 / Pages 177-195

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT07-A3811

Head Loss Characteristics of a Fibrous Bed in a PWR Chemical Environment

Ashok K. Ghosh, Kerry J. Howe, Arup K. Maji, Bruce C. Letellier, Russell C. Jones

Nuclear Technology / Volume 157 / Number 2 / February 2007 / Pages 196-207

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT07-A3812

Theoretical Analysis of the Working Performance of the Hydraulic Control Rod Driving System in Perturbation or Inclination

Yanhua Zheng, Hanliang Bo, Duo Dong

Nuclear Technology / Volume 157 / Number 2 / February 2007 / Pages 208-214

Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT07-A3813

The PROMETRA Program: Fuel Cladding Mechanical Behavior Under High Strain Rate

B. Cazalis, J. Desquines, C. Poussard, M. Petit, Y. Monerie, C. Bernaudat, P. Yvon, X. Averty

Nuclear Technology / Volume 157 / Number 3 / March 2007 / Pages 215-229

Technical Paper / Reactivity-Initiated Accident (RIA) / dx.doi.org/10.13182/NT07-A3814

Summary and Interpretation of the CABRI REP-Na Program

J. Papin, B. Cazalis, J. M. Frizonnet, J. Desquines, F. Lemoine, V. Georgenthum, F. Lamare, M. Petit

Nuclear Technology / Volume 157 / Number 3 / March 2007 / Pages 230-250

Technical Paper / Reactivity-Initiated Accident (RIA) / dx.doi.org/10.13182/NT07-A3815

Boiling Water Reactor Fuel Lattice Enrichment Distribution Optimization Using Tabu Search and Fuzzy Logic

Cecilia Martin-del-Campo, Juan Luis François, Alejandra M. Barragan, Miguel A. Palomera

Nuclear Technology / Volume 157 / Number 3 / March 2007 / Pages 251-260

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT07-A3816

Azimuthal Film-Boiling Heat Transfer from a Downward-Facing Hemisphere

Mong J. Yu, Chan S. Kim, Kune Y. Suh

Nuclear Technology / Volume 157 / Number 3 / March 2007 / Pages 261-276

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT07-A3817

Studies of an Accelerator-Driven Transuranium Burner with Hafnium-Based Inert Matrix Fuel

Kamil Tucek, Mikael Jolkkonen, Janne Wallenius, Waclaw Gudowski

Nuclear Technology / Volume 157 / Number 3 / March 2007 / Pages 277-298

Technical Paper / Accelerators / dx.doi.org/10.13182/NT07-A3818

Performance of Advanced Self-Shielding Models in DRAGON for the Estimation of CANDU-6 Safety Parameters

Ramamoorthy Karthikeyan, Alain Hébert

Nuclear Technology / Volume 157 / Number 3 / March 2007 / Pages 299-316

Technical Note / Fission Reactors / dx.doi.org/10.13182/NT07-A3819