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Volume 176

Number 1

Aging Tests of Neutron-Shielding Materials for Transport of Storage Casks

Herve Issard, Pascale Abadie

Nuclear Technology / Volume 176 / Number 1 / October 2011 / Pages 2-8

Special Issue Technical Paper / Second Seminar on Accelerated Testing of Materials in Spent Nuclear Fuel and High-Level Waste Storage Systems / Materials for Nuclear Systems

Accelerated Testing of Neutron-Absorbing Alloys for Nuclear Criticality Control

R. E. Mizia, T. E. Lister

Nuclear Technology / Volume 176 / Number 1 / October 2011 / Pages 9-21

Special Issue Technical Paper / Second Seminar on Accelerated Testing of Materials in Spent Nuclear Fuel and High-Level Waste Storage Systems / Materials for Nuclear Systems

Combined Experimental and Computational Approach to Predict the Glass-Water Reaction

E. M. Pierce, D. H. Bacon

Nuclear Technology / Volume 176 / Number 1 / October 2011 / Pages 22-39

Special Issue Technical Paper / Second Seminar on Accelerated Testing of Materials in Spent Nuclear Fuel and High-Level Waste Storage Systems / Radioactive Waste Management and Disposal

Feasibility of Reduced Boron Concentration Operation in Pressurized Water Reactor Plants

Aung Tharn Daing, Myung-Hyun Kim

Nuclear Technology / Volume 176 / Number 1 / October 2011 / Pages 40-56

Technical Paper / Second Seminar on Accelerated Testing of Materials in Spent Nuclear Fuel and High-Level Waste Storage Systems / Fission Reactors

Flashing-Induced Instability Analysis and the Start-Up of Natural Circulation Boiling Water Reactors

Rui Hu, Mujid S. Kazimi

Nuclear Technology / Volume 176 / Number 1 / October 2011 / Pages 57-71

Technical Paper / Second Seminar on Accelerated Testing of Materials in Spent Nuclear Fuel and High-Level Waste Storage Systems / Fission Reactors

Automatic Boiling Water Reactor Control Rod Pattern Design Using Ant Colony Optimization Algorithm

Cheng-Der Wang, Chaung Lin

Nuclear Technology / Volume 176 / Number 1 / October 2011 / Pages 72-82

Technical Paper / Second Seminar on Accelerated Testing of Materials in Spent Nuclear Fuel and High-Level Waste Storage Systems / Fission Reactors

Experimental Study on the Behavior of Suspended Aerosols of Sodium and Nonradioactive Fission Products (SrO2 and CeO2) in a Closed Vessel

V. Subramanian, R. Baskaran, J. Misra, R. Indira

Nuclear Technology / Volume 176 / Number 1 / October 2011 / Pages 83-92

Reactor Safety

Analysis of the BR2 Loss-of-Flow Test A

Constantine P. Tzanos, B. Dionne

Nuclear Technology / Volume 176 / Number 1 / October 2011 / Pages 93-105

Thermal Hydraulics

Using the Levenberg-Marquardt Method for Solutions of Inverse Transport Problems in One- and Two-Dimensional Geometries

Keith C. Bledsoe, Jeffrey A. Favorite, Tunc Aldemir

Nuclear Technology / Volume 176 / Number 1 / October 2011 / Pages 106-126

Radiation Transport and Protection

High-Performance Differential Pressure Monitoring Devices Using Pulsating Sensors for a Sodium-Cooled Fast Breeder Reactor

K. Praveen, M. P. Rajiniganth, A. D. Arun, R. Ananthanarayanan, N. Malathi, P. Sahoo, N. Murali

Nuclear Technology / Volume 176 / Number 1 / October 2011 / Pages 127-137

Nuclear Plant Operations and Control

Yucca Mountain Waste Package Closure System Robotic Welding and Inspection System

C. I. Nichol, D. P. Pace, E. D. Larsen, T. R. McJunkin, D. E. Clark, M. L. Clark, K. L. Skinner, A. D. Watkins, H. B. Smartt

Nuclear Technology / Volume 176 / Number 1 / October 2011 / Pages 138-146

Radioactive Waste Management and Disposal

Hot-Test Results of the Advanced Spent Fuel Conditioning Process Safeguards Neutron Counter for PWR Spent Fuel Rods

Tae-Hoon Lee, Young Soo Kim, Hee-Sung Shin, Ho-Dong Kim

Nuclear Technology / Volume 176 / Number 1 / October 2011 / Pages 147-154

Radiation Measurements and General Instrumentation

 
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