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General Kenneth Nichols and the Manhattan Project
Nichols
The Oak Ridger has published the latest in a series of articles about General Kenneth D. Nichols, the Manhattan Project, and the 1954 Atomic Energy Act. The series has been produced by Nichols’ grandniece Barbara Rogers Scollin and Oak Ridge (Tenn.) city historian David Ray Smith. Gen. Nichols (1907–2000) was the district engineer for the Manhattan Engineer District during the Manhattan Project.
As Smith and Scollin explain, Nichols “had supervision of the research and development connected with, and the design, construction, and operation of, all plants required to produce plutonium-239 and uranium-235, including the construction of the towns of Oak Ridge, Tennessee, and Richland, Washington. The responsibility of his position was massive as he oversaw a workforce of both military and civilian personnel of approximately 125,000; his Oak Ridge office became the center of the wartime atomic energy’s activities.”
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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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.13182/NT07-A3858
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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.13182/NT07-A3867
Introduction to the Beryllium Technology Special Issue
Glen R. Longhurst
Nuclear Technology | Volume 159 | Number 3 | September 2007 | Page 227
Technical Paper | Beryllium Technology | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.13182/NT07-A3879
