The Reed College Reactor Facility has been used for research and educational projects in the Portland area since its establishment in 1968. Cooperative programs between Reed and several public and private high schools, colleges, and universities in northwestern Oregon were established in 1970 through the Nuclear Science Consortium of the Willamette Valley. These programs have been an important part of the educational picture of the region.
The Reed College Reactor is a TRIGA Mark I water-cooled, "swimming pool" reactor at the bottom of a 25-foot-deep tank. It uses 58 zirconium hydride/uranium hydride fuel elements in a circular grid array. The uranium fuel is enriched to 20 percent in uranium-235. The reactor is surrounded by a graphite ring which minimizes neutron leakage by reflecting neutrons back into the core. Most reactor components are clad with aluminum.
The reactor can operate at any power up to the license ceiling of 250 kW. This makes it possible to provide a defined neutron flux as required for the experiment. The power level is usually maintained for periods ranging from a few minutes up to eight hours. Continued or repeated operation over several days is possible for longer irradiations.
Editors [1]
The following is the list of scholars from Reed College who currently serve as editors for one or more SciTechnol journals.
Publications [5]
The following is the list of articles by scholars from Reed College that are published in SciTechnol journals.
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Evaluation of Gas Turbine Performances and Nox and CO Emissions during the Steam Injection in the Upstream of Combustion Chamber
Research Article: J Nucl Ene Sci Power Generat Technol 2017, 6:4
DOI: 10.4172/2325-9809.1000176
Bouam A, Dadda A and Kadi R
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Applications of Green Composites in Immobilization of Radioactive Wastes and Others- A Review
Review Article: J Nucl Ene Sci Power Generat Technol 2017, 6:4
DOI: 10.4172/2325-9809.1000177
Saleh HM and Bayoumi TA
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Influence of Aluminum Addition on the Corrosion of 304 Stainless Steel in High Temperature Water
Research Article: J Nucl Ene Sci Power Generat Technol 2017, 6:4
DOI: 10.4172/2325-9809.1000178
Xiao-Fang Song, Sheng-Han Zhang and Ke-Gang Zhang
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Comparison of Corrosion Resistance for 304 and 316 Stainless Steel in the Simulated Primary Circuit of PWR
Research Article: J Nucl Ene Sci Power Generat Technol 2017, 6:4
DOI: 10.4172/2325-9809.1000179
Sheng-Han Zhang and Xiao-Fang Song
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Proton Irradiation Effects on the Physio-Mechanical Properties and Microstructure of Cold-Worked Molybdenum$
Research Article: J Nucl Ene Sci Power Generat Technol 2017, 6:4
DOI: 10.4172/2325-9809.1000180
Simos N, Quaranta E, Charitonidis N, Redaelli S, Bertarelli A, Mariani N, Zhong Z, Ghose S, Doorhyee E, Zhong H and Kotsina Z