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Volume 159

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Number 1

The Near Boiling Reactor: Design of a Small, Inherently Safe, Nuclear Reactor to Extend the Operational Envelope of the Victoria-Class Submarine

Christopher Cole, Hugues Bonin

Nuclear Technology / Volume 159 / Number 1 / July 2007 / Pages 1-14

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT07-A3852

Assessment of Regenerative Reheating in Direct Brayton Power Cycles for High-Temperature Gas-Cooled Reactors

Luis E. Herranz, José I. Linares, Beatriz Y. Moratilla

Nuclear Technology / Volume 159 / Number 1 / July 2007 / Pages 15-24

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT07-A3853

Probabilistic Risk Management Using Risk-Based Safety Goals for the Design of Spacecraft with Onboard Nuclear Reactor Systems

Michael V. Frank, William E. Kastenberg

Nuclear Technology / Volume 159 / Number 1 / July 2007 / Pages 25-38

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT07-A3854

Experiments on a Water Pool-Type Reactor Cavity Cooling System in a High-Temperature Gas-Cooled Reactor

Hyoung Kyu Cho, Yun Je Cho, Moon Oh Kim, Goon Cherl Park

Nuclear Technology / Volume 159 / Number 1 / July 2007 / Pages 39-58

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT07-A3855

Adsorption of Uranium on a Novel Bioadsorbent-Chitosan-Coated Perlite

Shameem Hasan, Tushar K. Ghosh, Mark A. Prelas, Dabir S. Viswanath, Veera M. Boddu

Nuclear Technology / Volume 159 / Number 1 / July 2007 / Pages 59-71

Technical Paper / Reprocessing / dx.doi.org/10.13182/NT07-A3856

Advances in the Subcritical, Gas-Cooled, Fast Transmutation Reactor Concept

W. M. Stacey, K. A. Boakye, S. K. Brashear, A. C. Bryson, K. A. Burns, E. J. Bruch, S. A. Chandler, O. M. Chen, S. S. Chiu, J.-P. Floyd, C. J. Fong, S. P. Hamilton, P. B. Johnson, S. M. Jones, M. Kato, B. A. MacLaren, R. P. Manger, B. L. Meriwether, C. Mitra, K. R. Riggs, B. H. Shrader, J. C. Schulz, C. M. Sommer, T. S. Sumner, J. S. Wagner, J. B. Weathers, C. P. Wells, F. H. Willis, Z. W. Friis, J. I. Marquez-Danian, R. W. Johnson, C. de Oliveira, H. K. Park, D. W. Tedder

Nuclear Technology / Volume 159 / Number 1 / July 2007 / Pages 72-105

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT07-A3857

The Design, Construction, and Preliminary Experiment of China's ADS Subcritical Experimental Assembly Venus-1

Yong-Qian Shi, Pu Xia, Zhang-Lin Luo, Zhi-Xiang Zhao, Dazhao Ding, Yi-Guo Li, Qin-Fu Zhu, Hai-Hong Xia, Ji-Gen Li, Wei Zhang, Jian Cao, Yan-Hui Quan, Huang-Da Luo, Xiaofei Wu

Nuclear Technology / Volume 159 / Number 1 / July 2007 / Pages 106-118

Technical Paper / Accelerators / dx.doi.org/10.13182/NT07-A3858

Number 2

Lithium-6-Based Passive Reactivity Control Devices for a Gas-Cooled Fast Reactor

W. F. G. van Rooijen, J. L. Kloosterman, T. H. J. J. van der Hagen, H. van Dam

Nuclear Technology / Volume 159 / Number 2 / August 2007 / Pages 119-133

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT07-A3859

Characteristics and Behavior of High-Burnup Fuel That May Affect the Source Terms for Cask Accidents

Robert E. Einziger, Carl Beyer

Nuclear Technology / Volume 159 / Number 2 / August 2007 / Pages 134-146

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT07-A3860

Optimization of the Hybrid Sulfur Cycle for Nuclear Hydrogen Generation

Yong Hoon Jeong, Mujid S. Kazimi

Nuclear Technology / Volume 159 / Number 2 / August 2007 / Pages 147-157

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT07-A3861

A Three-Dimensional CFD Model for a Performance Verification of the Liquid Poison Injection System of a CANDU-6 Reactor

Bo Wook Rhee, Hangbok Choi, Joo Hwan Park, Kyung Myung Chae, Hye Jeong Yun

Nuclear Technology / Volume 159 / Number 2 / August 2007 / Pages 158-166

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT07-A3862

Methodologies for the Probabilistic Risk Assessment of Digital Reactor Protection and Control Systems

Tunc Aldemir, Don W. Miller, Michael Stovsky, Jason Kirschenbaum, Paolo Bucci, L. Anthony Mangan, Audeen Fentiman, Steven A. Arndt

Nuclear Technology / Volume 159 / Number 2 / August 2007 / Pages 167-191

Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT07-A3863

Fire Durations of Concern for a Modern Legal-Weight Truck Cask

Neelima Mallidi, Miles Greiner, Venkata V. R. Venigalla

Nuclear Technology / Volume 159 / Number 2 / August 2007 / Pages 192-201

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT07-A3864

Real-Time Measurement of Material Elastic Properties in a High Gamma Irradiation Environment

R. S. Schley, K. L. Telschow, J. B. Walter, D. L. Cottle

Nuclear Technology / Volume 159 / Number 2 / August 2007 / Pages 202-207

Technical Paper / Materials for Nuclear Systems / dx.doi.org/10.13182/NT07-A3865

Monte Carlo Modeling of Count Rates and Defects in a Silicon Carbide Detector Neutron Monitor System, Highlighting GT-MHR

Behrooz Khorsandi, Mehdi Reisi Fard, Thomas E. Blue, Don W. Miller, Wolfgang Windl

Nuclear Technology / Volume 159 / Number 2 / August 2007 / Pages 208-220

Technical Paper / Radiation Measurements and Instrumentation / dx.doi.org/10.13182/NT07-A3866

Highly Sensitive Laser Diode Detection of CsCl

Edward Augustyniak, Aleksander Ershov, Jacek Borysow

Nuclear Technology / Volume 159 / Number 2 / August 2007 / Pages 221-226

Technical Note / Radiation Measurements and Instrumentation / dx.doi.org/10.13182/NT07-A3867

Number 3

Introduction to the Beryllium Technology Special Issue

Glen R. Longhurst

Nuclear Technology / Volume 159 / Number 3 / September 2007 / Page 227

Technical Paper / Beryllium Technology / dx.doi.org/10.13182/NT07-A3868

Effect of Ti Content on Compatibility Between Be-Ti and SS316LN

K. Tsuchiya, H. Kawamura, T. Ishida

Nuclear Technology / Volume 159 / Number 3 / September 2007 / Pages 228-232

Technical Paper / Beryllium Technology / dx.doi.org/10.13182/NT07-A3869

Structural and Oxidation Studies of Titanium Beryllides

E. Alves, L. C. Alves, N. Franco, M. R. Da Silva, A. Paúl

Nuclear Technology / Volume 159 / Number 3 / September 2007 / Pages 233-237

Technical Paper / Beryllium Technology / dx.doi.org/10.13182/NT07-A3870

Beryllium Layer Deposition on Carbon and Tungsten from Beryllium-Seeded Plasmas

K. Schmid, M. J. Baldwin, R. P. Doerner, D. Nishijima

Nuclear Technology / Volume 159 / Number 3 / September 2007 / Pages 238-244

Technical Paper / Beryllium Technology / dx.doi.org/10.13182/NT07-A3871

Magnetic Field Effects on Tritium Release from Neutron-Irradiated Beryllium Pebbles

Juris Tiliks, Gunta Kizane, Aigars Vitins, Elina Kolodinska, Elisa Rabaglino

Nuclear Technology / Volume 159 / Number 3 / September 2007 / Pages 245-249

Technical Paper / Beryllium Technology / dx.doi.org/10.13182/NT07-A3872

Use of a Paraffin-Based Grout to Stabilize Buried Beryllium and Other Wastes

Gretchen E. Matthern, Neal A. Yancey, Darrel L. Knudson, Duane J. Hanson

Nuclear Technology / Volume 159 / Number 3 / September 2007 / Pages 250-255

Technical Paper / Beryllium Technology / dx.doi.org/10.13182/NT07-A3873

Automatic Search of the Power Ascension Path for a Boiling Water Reactor Using Genetic Algorithm and Neural Network

Chi-Szu Lee, Chaung Lin

Nuclear Technology / Volume 159 / Number 3 / September 2007 / Pages 256-266

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT07-A3874

A Modular Metal-Fuel Fast Reactor with One-Loop Main Cooling System

Yoshitaka Chikazawa, Yasushi Okano, Mamoru Konomura, Koji Sato, Naoki Sawa, Hiroyuki Sumita, Shigeyuki Nakanishi, Masato Ando

Nuclear Technology / Volume 159 / Number 3 / September 2007 / Pages 267-278

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT07-A3875

Liquid-Metal Bond for LWR Fuel Rods

Doonyapong Wongsawaeng, Donald Olander

Nuclear Technology / Volume 159 / Number 3 / September 2007 / Pages 279-291

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT07-A3876

Simulation of Two-Phase Flow in Complex Systems

Wolfgang Wulff

Nuclear Technology / Volume 159 / Number 3 / September 2007 / Pages 292-309

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT07-A3877

Natural Convection's Transient Behavior

S. Usman, B. S. Mohammad, S. Abdallah

Nuclear Technology / Volume 159 / Number 3 / September 2007 / Pages 310-318

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT07-A3878

A Methodology for Experimental and 3-D Computational Radiation Transport Assessments of Pu-Be Neutron Sources

Gabriel Ghita, Glenn Sjoden, James Baciak

Nuclear Technology / Volume 159 / Number 3 / September 2007 / Pages 319-331

Technical Paper / Radiation Protection / dx.doi.org/10.13182/NT07-A3879