ANS / Publications / Journals / Nuclear Technology

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 / dx.doi.org/10.13182/NT11-A12538

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 / dx.doi.org/10.13182/NT11-A12539

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 / dx.doi.org/10.13182/NT11-A12540

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 / dx.doi.org/10.13182/NT176-40

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 / dx.doi.org/10.13182/NT11-A12542

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 / dx.doi.org/10.13182/NT11-A12543

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 / dx.doi.org/10.13182/NT11-A12544

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 / dx.doi.org/10.13182/NT11-A12545

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 / dx.doi.org/10.13182/NT176-106