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Reed College

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.
Melinda Krahenbuhl

Publications [7]

The following is the list of articles by scholars from Reed College that are published in SciTechnol journals.
On Electrochemical Maintaining of the Given Quality of Molten Salt Reactors
Research Article:  J Nucl Ene Sci Power Generat Technol 2017, 6:1
doi: 10.4172/2325-9809.1000163
Electrochemical maintaining; Molten salt reactors; Quality
Abstract  |   Full-text  |   PDF  |  
Measurement of U diffusion in Nb using alpha-Spectrometry
Research Article:  J Nucl Ene Sci Power Generat Technol 2017, 6:1
doi: 10.4172/2325-9809.1000164
Perez Rodolfo A, Gordillo Jorge A, Iribarren M, Di Lalla N
Abstract  |   Full-text  |   PDF  |  
Investigation on Heat Transfer Behaviour of Molten Salt Natural Circulation Loop using Numerical Simulations
Research Article:  J Nucl Ene Sci Power Generat Technol 2017, 6:1
doi: 10.4172/2325-9809.1000165
Jayaraj Yallappa Kudariyawar, Abhijeet Mohan Vaidya, Naresh Kumar Maheshwari, Polepalle Satyamurthy, Abhishek Kumar Srivatsav, Babalu Mohan Lingade
Abstract  |   Full-text  |   PDF  |  
Burn up Effects on Kinetic Parameter’s Variations in an Electron Accelerator Driven Subcritical Reactor
Research Article:  J Nucl Ene Sci Power Generat Technol 2017, 6:1
doi: 10.4172/2325-9809.1000166
Ebrahimkhani Mm, Hassanzadeh M, Feghhi SAH3 and Rahbari K
Abstract  |   Full-text  |   PDF  |  
Proliferation Resistance and Safeguardability of Different Fuel Cycles
Research Article:  J Nucl Ene Sci Power Generat Technol 2017, 6:1
doi: 10.4172/2325-9809.1000167
Gangotra S, Sharma G, Viswanadham CS
Abstract  |   Full-text  |   PDF  |  
Evaluation of Uranium, Thorium and Some Metal Elements in Rocks by HR-ICP-MS and LIBS
Research Article:  J Nucl Ene Sci Power Generat Technol 2017, 6:1
doi: 10.4172/2325-9809.1000168
Fathi M Ibrahim A Sergani, Abdelrazig Mohamed Abdelbagi and Abdelaziz AMEL Shokali
Abstract  |   Full-text  |   PDF  |  
Effect of Aqueous Phase Acidity on Thermal and Radiolytic Degradation Behaviour of PUREX Solvent
Research Article:  J Nucl Ene Sci Power Generat Technol 2017, 6:1
doi: 10.4172/2325-9809.1000169
Mishra S, Mallika C, Pandey NK, Kamachi Mudali U
Abstract  |   Full-text  |   PDF  |  
 
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