Dynamic analysis of a TRIGA reactor
Creators
- 1. National Atomic Energy Agency (PAA), Warsaw (Poland)
- 2. US Nuclear Regulatory Commission, Office of International Programs, Rockville, Maryland (United States)
- 3. Brookhaven National Laboratory, Nuclear Science and Technology Department, Upton, New York (United States)
Description
Nuclear energy offers long-term economic and environmental benefits providing a reliable energy source with significant environmental advantages in reducing the effect of human activities on global warming. National governments in countries operating or planning to establish nuclear facilities have instituted regulatory regimes on the use of nuclear materials and facilities to insure a high level of operational safety. Research and Test Reactors (RTRs) play a significant role as research, training, and development facilities providing scientific bases and expertise for nuclear power programs. TRIGA-type reactors play a significant role as one of the most widely used research and training reactors in the world utilized for many diverse fields of applications. TRIGA installations have a unique, pulsing capability allowing the thermal power to reach very high levels for a very short period of time. The paper presents the results of a dynamic analysis of a TRIGA reactor using the coupled PARCS/TRACE code system. A pin-wise PARCS neutronic model was developed coupled to a simplified TRACE thermal-hydraulic representation of the reactor pool. Power pulse analysis from low and operating power level and the consequent peak power and temperature behavior suggest that present Technical Specification limits on fuel temperatures for pulsing is adequate to insure the safe operation of the TRIGA reactors. The study validates presently accepted methodologies and provides further assurances that TRIGA reactors can safely be pulsed and operated as research and training reactors. (author)
Additional details
Identifiers
Publishing Information
- Publisher
- European Nuclear Society
- Imprint Place
- Brussels (Belgium)
- ISBN
- 978-92-95064-25-6
- Imprint Title
- European Research Reactor Conference (RRFM) 2016: Conference Proceedings
- Imprint Pagination
- 1154 p.
- Journal Page Range
- p. 791-798
- Report number
- INIS-BE--16M5704
Conference
- Title
- 20. international topical meeting on Research Reactor Fuel Management (RRFM)
- Acronym
- RRFM 2016
- Dates
- 13-17 Mar 2016
- Place
- Berlin (Germany)
INIS
- Country of Publication
- Belgium
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 49023274
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- GREENHOUSE EFFECT; NUCLEAR FACILITIES; NUCLEAR POWER; PEAK LOAD; PLANNING; REACTOR SAFETY; THERMAL HYDRAULICS; TRAINING REACTORS; TRIGA TYPE REACTORS
- Descriptors DEC
- CLIMATIC CHANGE; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HOMOGENEOUS REACTORS; HYDRAULICS; HYDRIDE MODERATED REACTORS; MECHANICS; POWER; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; SOLID HOMOGENEOUS REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- © European Nuclear Society, 2003; 4 refs., 2 figs., 5 tabs.s.; This record replaces 48058209
- Secondary number(s)
- RRFM2016--A0190