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Volume 167

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Thermal-Hydraulic Aspects of Progression to Severe Accidents in CANDU Reactors

John C. Luxat

Nuclear Technology / Volume 167 / Number 1 / Pages 187-210

July 2009

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Experimental Study on the Boiling Heat Removal at the Upper Surface of the Metallic Layer During Late-Phase Coolant Injection

Kyoung-Ho Kang, Rae-Joon Park, Sang-Baik Kim, Seong-Wan Hong

Nuclear Technology / Volume 167 / Number 1 / Pages 211-222

July 2009

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Dynamics and Preconditioning in a Single-Droplet Vapor Explosion

Roberta Concilio Hansson, Hyun Sun Park, Truc-Nam Dinh

Nuclear Technology / Volume 167 / Number 1 / Pages 223-234

July 2009

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Improvement of Core Modeling in ICARE/CATHARE: Application to the Calculation of a Six-Inch-Break LOCA Leading to a Severely Degraded Situation

Patrick Drai, Olivier Marchand, Patrick Chatelard, Florian Fichot, Joëlle Fleurot

Nuclear Technology / Volume 167 / Number 1 / Pages 235-246

July 2009

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Simplification of the Severe Accident Management Guideline for the Containment Flooding in a Mark-III Containment

Min-Jie Chuang, Shih-Jen Wang, Sheng-Yuan Fann, Show-Chyuan Chiang

Nuclear Technology / Volume 167 / Number 2 / Pages 247-253

August 2009

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Feasibility Study on an Upgraded Future Monju Core Concept with Extended Operation Cycle Length of One Year and Increased Fuel Burnup

Hidehito Kinjo, Takeshi Kageyama, Akihiro Kitano, Shin Usami

Nuclear Technology / Volume 167 / Number 2 / Pages 254-267

August 2009

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Sensitivity and Uncertainty Analysis of Commercial Reactor Criticals for Burnup Credit

Georgeta Radulescu, Donald E. Mueller, John C. Wagner

Nuclear Technology / Volume 167 / Number 2 / Pages 268-287

August 2009

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Analysis of a Generic Liquid-Metal Leak

K. Samec, R. Z. Milenkovic

Nuclear Technology / Volume 167 / Number 2 / Pages 288-303

August 2009

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Analysis of Leaks Through Microchannel Cracks Using RELAP5-3D

Angelo Frisani, Yassin A. Hassan

Nuclear Technology / Volume 167 / Number 2 / Pages 304-312

August 2009

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Use of Geometrically Accurate Fuel Models to Predict Cladding and Basket Temperatures Within a Truck Cask During Normal Transport

Venkata V. R. Venigalla, Miles Greiner

Nuclear Technology / Volume 167 / Number 2 / Pages 313-324

August 2009

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Dimensionless Numbers in Phase-Change Thermosyphon and Heat-Pipe Heat Exchangers

Piyush Sabharwall, Vivek Utgikar, Fred Gunnerson

Nuclear Technology / Volume 167 / Number 2 / Pages 325-332

August 2009

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Extraction of U(VI) by Tri-n-Amyl Phosphate Under High Solvent Loading Conditions

A. Suresh, N. L. Sreenivasan, Robert Selvan, M. P. Antony, T. G. Srinivasan, S. B. Koganti, P. R. Vasudeva Rao

Nuclear Technology / Volume 167 / Number 2 / Pages 333-338

August 2009

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Hazard Assessment of the CIRCE Lead-Bismuth Experimental Facility in the ICE Configuration

Luciano Burgazzi

Nuclear Technology / Volume 167 / Number 3 / Pages 339-347

September 2009

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Feasibility Study on a Simplified MOX Pellet Fabrication Process, the Short Process, for Fast Breeder Reactor Fuel

Koichi Asakura, Kentaro Takeuchi, Takayoshi Makino, Yoshiyuki Kato

Nuclear Technology / Volume 167 / Number 3 / Pages 348-361

September 2009

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Use of Isotopically Modified Erbium in Advanced LWR Fuel

Fausto Franceschini, Bojan Petrovic

Nuclear Technology / Volume 167 / Number 3 / Pages 362-370

September 2009

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Benchmark of Computational Fluid Dynamics Simulations Using Temperatures Measured Within Enclosed Vertical and Horizontal Arrays of Heated Rods

N. R. Chalasani, Pablo E. Araya, Miles Greiner

Nuclear Technology / Volume 167 / Number 3 / Pages 371-383

September 2009

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Price:$30.00

Benchmark of Natural Convection/Radiation Simulations Within an Enclosed Array of Horizontal Heated Rods

Pablo E. Araya, Miles Greiner

Nuclear Technology / Volume 167 / Number 3 / Pages 384-394

September 2009

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Price:$30.00

Calculation of Photon Exposure and Ambient Dose Slant-Path Buildup Factors for Radiological Assessment

Fritz G. Schirmers, Adam Davis, H. Omar Wooten, Donald J. Dudziak, Man-Sung Yim, David McNelis

Nuclear Technology / Volume 167 / Number 3 / Pages 395-409

September 2009

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Price:$30.00

Ammonium Polyuranate Precipitation from Fluoride Solutions: An Experimental Study of the UO3-HF-NH3-H2O System as Applied in UF6 Processing

A. B. Rothman, D. G. Graczyk

Nuclear Technology / Volume 167 / Number 3 / Pages 410-420

September 2009

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Price:$30.00

Book Review

Nicholas Tsoulfanidis

Nuclear Technology / Volume 167 / Number 3 / Page 421

September 2009

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