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ANS > Publications > Journals > Nuclear Technology > Volume 157
Number 1  ·  Number 2  ·  Number 3
Number 1 · January 2007
Table of Contents
Progress of the DUPIC Fuel Compatibility Analysis - IV: Fuel Performance
Volume 157 · Number 1 · January 2007 · Pages 1-17
Technical Paper · Fission Reactors

Hangbok Choi, Ho Jin Ryu, Gyuhong Roh, Chang Joon Jeong, Chang Je Park, Kee Chan Song, Jung Won Lee, Myung Seung Yang
Comparative Transient Analysis of Critical and Subcritical 80-MW Pb-Bi Eutectic-Cooled Reactor Systems
Volume 157 · Number 1 · January 2007 · Pages 18-36
Technical Paper · Reactor Safety

K. Mikityuk, P. Coddington, S. Pelloni, E. Bubelis, R. Chawla
Zirconium Matrix Cermet for a Mixed Uranium-Thorium Oxide Fuel in an SBWR
Volume 157 · Number 1 · January 2007 · Pages 37-52
Technical Paper · Fuel Cycle and Management

Sean M. McDeavitt, Yunlin Xu, Thomas J. Downar, Alvin A. Solomon
Improvement of Fuel Performance Code COSMOS with Recent In-Pile Data for MOX and UO2 Fuels
Volume 157 · Number 1 · January 2007 · Pages 53-64
Technical Paper · Fuel Cycle and Management

Byung-Ho Lee, Yang-Hyun Koo, Je-Yong Oh, Jin-Sik Cheon, Dong-Seong Sohn
Integrator Circuit as an Analogy for Convection
Volume 157 · Number 1 · January 2007 · Pages 65-73
Technical Paper · Thermal Hydraulics

S. Usman, S. Abdallah, M. Hawwari, M. Scarangella, L. Shoaib
Water Adsorption Isotherms for Charged and Uncharged Cesium Iodide Aerosol Particles
Volume 157 · Number 1 · January 2007 · Pages 74-86
Technical Paper · Nuclear Plant Operations and Control

Charles A. Riggs, Robert V. Tompson, Tushar K. Ghosh, Sudarshan K. Loyalka, Dabir S. Viswanath
Environmental Impact of Yucca Mountain Repository in the Case of Canister Failure
Volume 157 · Number 1 · January 2007 · Pages 87-105
Technical Paper · Radioactive Waste Management and Disposal

Joonhong Ahn
Dead-Time Correction for Nonparalyzing Detectors When Measuring Short-Lived Nuclides
Volume 157 · Number 1 · January 2007 · Pages 106-109
Technical Paper · Radiation Measurements and Instrumentation

Andrija S. Radovic, Shoaib Usman
Number 2 · February 2007
Table of Contents
Research and Development on System Integration Technology for Connection of Hydrogen Production System to an HTGR
Volume 157 · Number 2 · February 2007 · Pages 111-119
Technical Paper · Fission Reactors

Yoshiyuki Inagaki, Hirofumi Ohashi, Yoshitomo Inaba, Hiroyuki Sato, Tetsuo Nishihara, Tetsuaki Takeda, Koji Hayashi, Masuro Ogawa
A Compact Loop-Type Fast Reactor Without Refueling for a Remote Area Power Source
Volume 157 · Number 2 · February 2007 · Pages 120-131
Technical Paper · Fission Reactors

Yoshitaka Chikazawa, Yasushi Okano, Mamoru Konomura, Naoki Sawa, Yoshio Shimakawa, Toshihiko Tanaka
Benchmark Study on Fuel Bundle Degradation in the Phebus FPT3 Test Using the Severe Accident Codes ATHLET-CD, ICARE2, and MELCOR
Volume 157 · Number 2 · February 2007 · Pages 132-142
Technical Paper · Fuel Cycle and Management

Bela Toth, Klaus Mueller, Jon Birchley, Hozumi Wada, Claude Jamond, Klaus Trambauer
Proliferation Resistance Assessment Methodology for Nuclear Fuel Cycles
Volume 157 · Number 2 · February 2007 · Pages 143-156
Technical Paper · Fuel Cycle and Management

William S. Charlton, Ryan F. LeBouf, Claudio Gariazzo, D. Grant Ford, Carl Beard, Sheldon Landsberger, Michael Whitaker
Fertile-Free Fuels in Pressurized Water Reactors: Design Challenges and Solutions
Volume 157 · Number 2 · February 2007 · Pages 157-176
Technical Paper · Fuel Cycle and Management

E. Fridman, E. Shwageraus, A. Galperin
Validation of Coupled Thermal-Hydraulic and Neutronics Codes for Safety Analysis by International Cooperations
Volume 157 · Number 2 · February 2007 · Pages 177-195
Technical Paper · Thermal Hydraulics

Kostadin Ivanov, Enrico Sartori, E. Royer, S. Langenbuch, K. Velkov
Head Loss Characteristics of a Fibrous Bed in a PWR Chemical Environment
Volume 157 · Number 2 · February 2007 · Pages 196-207
Technical Paper · Thermal Hydraulics

Ashok K. Ghosh, Kerry J. Howe, Arup K. Maji, Bruce C. Letellier, Russell C. Jones
Theoretical Analysis of the Working Performance of the Hydraulic Control Rod Driving System in Perturbation or Inclination
Volume 157 · Number 2 · February 2007 · Pages 208-214
Technical Paper · Nuclear Plant Operations and Control

Yanhua Zheng, Hanliang Bo, Duo Dong
Number 3 · March 2007
Table of Contents
The PROMETRA Program: Fuel Cladding Mechanical Behavior Under High Strain Rate
Volume 157 · Number 3 · March 2007 · Pages 215-229
Technical Paper · Reactivity-Initiated Accident (RIA)

B. Cazalis, J. Desquines, C. Poussard, M. Petit, Y. Monerie, C. Bernaudat, P. Yvon, X. Averty
Summary and Interpretation of the CABRI REP-Na Program
Volume 157 · Number 3 · March 2007 · Pages 230-250
Technical Paper · Reactivity-Initiated Accident (RIA)

J. Papin, B. Cazalis, J. M. Frizonnet, J. Desquines, F. Lemoine, V. Georgenthum, F. Lamare, M. Petit
Boiling Water Reactor Fuel Lattice Enrichment Distribution Optimization Using Tabu Search and Fuzzy Logic
Volume 157 · Number 3 · March 2007 · Pages 251-260
Technical Paper · Fuel Cycle and Management

Cecilia Martin-del-Campo, Juan Luis François, Alejandra M. Barragan, Miguel A. Palomera
Azimuthal Film-Boiling Heat Transfer from a Downward-Facing Hemisphere
Volume 157 · Number 3 · March 2007 · Pages 261-276
Technical Paper · Thermal Hydraulics

Mong J. Yu, Chan S. Kim, Kune Y. Suh
Studies of an Accelerator-Driven Transuranium Burner with Hafnium-Based Inert Matrix Fuel
Volume 157 · Number 3 · March 2007 · Pages 277-298
Technical Paper · Accelerators

Kamil Tucek, Mikael Jolkkonen, Janne Wallenius, Waclaw Gudowski
Performance of Advanced Self-Shielding Models in DRAGON for the Estimation of CANDU-6 Safety Parameters
Volume 157 · Number 3 · March 2007 · Pages 299-316
Technical Note · Fission Reactors

Ramamoorthy Karthikeyan, Alain Hébert
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