Plant protection system optimization studies to mitigate consequences of large breaks in the advanced neutron source reactor
Creators
- 1. Oak Ridge Institute for Science and Education, TN (United States)
- 2. Oak Ridge National Lab., TN (United States)
Description
This paper documents some of the optimization studies performed to maximize the performance of the engineered safety features and scram systems to mitigate the consequences of large breaks in the primary cooling system of the advanced neutron source (ANS) reactor. The ANS is a new basic and applied research facility based on a powerful steady-state research reactor that provides beams of neutrons for measurements and experiments in the field of material science and engineering, biology, chemistry, material analysis, and nuclear science. To achieve the high neutron fluxes for these state-of-the-art experiments, the ANS design has a very high power density core (330 MWfission with an active volume of 67.6 ell) surrounded by a large heavy-water reflector, where most neutrons are moderated. This design maximizes the number of neutrons available for experiments but results in a low heat capacity core that creates unique challenges to the design of the plant protection system
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 69
- Journal Page Range
- p. 267-269.
- 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
- 26026195
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DESIGN; ENGINEERED SAFETY SYSTEMS; LOSS OF COOLANT; NEUTRON FLUX; POWER DENSITY; REACTOR PROTECTION SYSTEMS; REACTOR SAFETY; RESEARCH REACTORS; SAFETY ANALYSIS; SCRAM
- Descriptors DEC
- ACCIDENTS; RADIATION FLUX; REACTOR ACCIDENTS; REACTOR SHUTDOWN; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; SHUTDOWN
Optional Information
- Secondary number(s)
- CONF-931160--.