Physics and safety aspects of the minimum attention plant
Description
The Minimum Attention Plant design is based on a self-pressured, indirect-cycle light water reactor with multiple once-through steam generators located within the reactor vessel. Primary coolant flow is initiated and maintained solely by natural circulation. The design of the reactor system provides major operational and safety advantages compared to conventional designs rated at 500 MWe or less, as well as major simplifications and plant equipment reduction, without requiring significant departure from existing LWR technology. Reactor power changes throughout lifetime are accommodated through primary system pressure and temperature changes without requirement for soluble boron or control rod motion. The absence of external coolant loops and large pipe connections to the reactor vessel eliminates or limits major classes of potential accidents, including loss of flow, loss of coolant, and steam line break
Additional details
Publishing Information
- Imprint Title
- Proceedings of the topical meeting on reactor physics and safety: Sessions 1-10. Volume 1
- Journal Page Range
- p. 105-120.
- Report number
- NUREG/CP--0080-Vol.1
Conference
- Title
- Advances in reactor physics and safety meeting.
- Dates
- 17-19 Sep 1986.
- Place
- Saratoga Springs, NY (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 18019666
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- AVAILABILITY; BORON; CONTROL ELEMENTS; LOSS OF COOLANT; NATURAL CONVECTION; POWER DISTRIBUTION; PRESSURE VESSELS; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR PHYSICS; REACTOR SAFETY; RELIABILITY; RUPTURES; SPECIFICATIONS; STANDARDIZATION; STEAM GENERATORS; STEAM LINES
- Descriptors DEC
- ACCIDENTS; BOILERS; CONTAINERS; CONVECTION; COOLING SYSTEMS; DISTRIBUTION; ELEMENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FAILURES; HEAT TRANSFER; PIPELINES; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SAFETY; SEMIMETALS; SPATIAL DISTRIBUTION; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS