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.

The following is the list of scholars from Reed College who currently serve as editors for one or more SciTechnol journals.

• Melinda Krahenbuhl, PhD

The following is the list of articles by scholars from Reed College that are published in SciTechnol journals.

• Rotational Symmetry Boundary Condition in Current Coupled Whole Core Pin by Pin Transport Theory Code

  Research Article: J Nucl Ene Sci Power Generat Technol 2017, 6:2
  DOI: 10.4172/2325-9809.1000170
  

  Suhail Ahmad Khan, Jagannathan V, Umasankari Kannan
  

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• Empirical Formulae to Calculate Full-Energy Peak Attenuation Coefficients of Well-Type NaI (Tl) Detectors

  Research Article: J Nucl Ene Sci Power Generat Technol 2017, 6:2
  DOI: 10.4172/2325-9809.1000171
  Abbas MI¹, El-Bayoumi EM², Badawi MS^1,3*, Thabet AA⁴, El-Khatib AM¹ and Al-Mugren KS ⁵
  
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• Cask Selection for Spent Nuclear Fuel Shipment from Research Reactor

  Research Article: J Nucl Ene Sci Power Generat Technol 2017, 6:2
  DOI: 10.4172/2325-9809.1000172
  Kadalev S and Dimitrov I
  
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• Modeling of Small Size Divertor Tokamak in Discharge withEdge Transport Barrier (ETB)

  Research Article: J Nucl Ene Sci Power Generat Technol 2017, 6:2
  DOI: 10.4172/2325-9809.1000173
  Amr Hasheim Bekheit
  
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• Thermal Hydraulic Analysis and Modeling of the HTTR Using the RELAP5-3D

  Research Article: J Nucl Ene Sci Power Generat Technol 2017, 6:2
  DOI: 10.4172/2325-9809.1000174
  Scari ME, Costa AL*, Ramos MC and Pereira C
  
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• Lesson Learned from the February 2014 Fire and Radiation Release Events at the Waste Isolation Pilot Plant in New Mexico, USA

  Research Article: J Nucl Ene Sci Power Generat Technol 2017, 6:2
  DOI: 10.4172/2325-9809.1000175
  Thakur P, Hardy R
  
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• Conservation of “Cause-Effect” by using Integrated Individual Radiation Dosestowards Standardization of Epidemiology Health-Risk Estimates of Nuclear/Radiation Workers

  Editorial: J Nucl Ene Sci Power Generat Technol 2017, 6:2
  DOI: 10.4172/2325-9809.1000e106
  Sohrabi M
  
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