Potential for new societal contributions from the advanced test reactor
Description
The mission of the Advanced Test Reactor (ATR) at Idaho National Engineering Laboratory is to study the effects of intense radiation on materials and fuels and to produce radioisotopes for the U.S. Department of Energy (DOE) for government and commercial applications. The purpose of this paper is to explore the potential benefits to society from these available neutrons. The ATR is a 250-MW(thermal) light water reactor highly enriched uranium in plate-type fuel. The ATR uses a combination of hafnium control drums and shim rods to adjust power and hold flux distortion to a minimum. The different quadrants of the ATR can be operated at different power levels to meet a variety of mission requirements. Irradiation positions are available at various locations throughout the core and beryllium reflector. A summary of the flux levels at various ATR reflector and loop positions. is given. These fluxes are maintained with a relatively constant axial flux profile throughout cycles that last 35 to 42 days. These neutrons can be used for testing and irradiation programs that support commercial reactor license extension, advanced fuel development, materials effects studies, failure cause/effect studies, coolant chemistry evaluations, prototype testing programs, isotope production, and basic research. Radioisotope production falls into three categories: medical, industrial, and research. In summary, the ATR is a unique, high-power test reactor capable of supporting the current DOE mission and producing radioisotopes. Space available for radioisotope production and fuels or materials testing will increase by 44% in 1994, improving DOE's ability to support national needs in health care, industry, and research
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Additional details
Publishing Information
- Imprint Title
- IGORR-IV: Proceedings of the fourth meeting of the International Group On Research Reactors
- Imprint Pagination
- 426 p.
- Journal Page Range
- p. 1-4
- Report number
- CONF--9505218
Conference
- Title
- 4. meeting of the International Group On Research Reactors
- Dates
- 23-25 May 1995
- Place
- Gatlinburg, TN (United States)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 36023817
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ATR REACTOR; CONTROL ELEMENTS; FUEL PLATES; HAFNIUM; HIGHLY ENRICHED URANIUM; ISOTOPE PRODUCTION; MATERIALS TESTING; NEUTRON FLUX
- Descriptors DEC
- ACTINIDES; ELEMENTS; ENRICHED URANIUM; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; IRRADIATION REACTORS; ISOTOPE ENRICHED MATERIALS; MATERIALS; MATERIALS TESTING REACTORS; METALS; RADIATION FLUX; REACTOR COMPONENTS; REACTORS; REFRACTORY METALS; RESEARCH AND TEST REACTORS; TANK TYPE REACTORS; TEST FACILITIES; TEST REACTORS; TESTING; THERMAL REACTORS; TRANSITION ELEMENTS; URANIUM; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract DE-AC05-84OR21400
- Notes
- 1 ref., 1 fig., 2 tabs
- Secondary number(s)
- INIS-XA-C--026