Potential for new societal contributions from the advanced test reactor
Creators
- 1. Idaho National Engineering Lab., Idaho Falls, ID (United States)
Description
The mission of the Advanced Test Reactor (ATR) at the 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. Because of reductions in defense spending, four of the nine loop test spaces will become available in 1994. 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 with highly enriched uranium in plate-type fuel. Forty fuel elements are arranged in a serpentine pattern. 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 significantly different power levels to meet a variety of mission requirements. Irradiation positions are available at various locations throughout the core and beryllium reflector
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 69
- Journal Page Range
- p. 159-161.
- ISSN
- 0003-018X
- CODEN
- TANSAO
Conference
- Title
- American Nuclear Society (ANS) winter meeting.
- Dates
- 14-18 Nov 1993.
- Place
- San Francisco, CA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 26026215
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ATR REACTOR; IRRADIATION; NEUTRON SOURCE FACILITIES; RADIOISOTOPES; RESEARCH PROGRAMS
- Descriptors DEC
- ENRICHED URANIUM REACTORS; IRRADIATION REACTORS; ISOTOPES; MATERIALS TESTING REACTORS; REACTORS; RESEARCH AND TEST REACTORS; TANK TYPE REACTORS; TEST FACILITIES; TEST REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-931160--.