Loss of coolant analysis for the tower shielding reactor II
Creators
- 1. Research Reactors Div., Oak Ridge National Lab., Oak Ridge, TN (United States)
Description
The operational limits of the Tower Shielding Reactor-II (TSR-II) have been revised to account for placing the reactor in a beam shield, which reduces convection cooling during a loss-of-coolant accident (LOCA). This paper reports on a detailed heat transfer analysis performed to set operating time limits which preclude fuel damage during a LOCA. Since a LOCA is survivable, the pressure boundary need not be safety related, minimizing seismic and inspection requirements. Measurements of reactor component emittance for this analysis revealed that aluminum oxidized in water may have emittances much higher than accepted values, allowing higher operating limits than were originally expected. These limits could be increased further with analytical or hardware improvements
Additional details
Publishing Information
- Publisher
- American Nuclear Society.
- Imprint Place
- La Grange Park, IL (United States)
- Imprint Title
- The safety, status and future of non-commercial reactors and irradiation facilities
- Imprint Pagination
- 830 p.
- Journal Page Range
- p. 131-138.
Conference
- Title
- American Nuclear Society (ANS) topical meeting on the safety, status and future of non-commercial reactors and irradiation facilities.
- Dates
- 30 Sep - 4 Oct 1990.
- Place
- Boise, ID (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23036889
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALUMINIUM; HEAT TRANSFER; LOSS OF COOLANT; NUCLEAR DAMAGE; NUCLEAR FUELS; OXIDATION; REACTOR COMPONENTS; REACTOR OPERATION; RISK ASSESSMENT; SAFETY ANALYSIS; SHIELDING; TSR-2 REACTOR
- Descriptors DEC
- ACCIDENTS; CHEMICAL REACTIONS; ELEMENTS; ENERGY SOURCES; ENERGY TRANSFER; FUELS; MATERIALS; METALS; OPERATION; REACTOR ACCIDENTS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; TEST FACILITIES; TEST REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-900917--.