LEIBSTADT/STP-2001, BWR/6, Reactor Core Isolation Cooling System Test
Description
1 - Description of test facility: The Leibstadt Nuclear Power Station is equipped with a direct cycle boiling water reactor belonging to the General Electric BWR product line BWR/6. The MARK III containment system encloses the nuclear island. The nuclear system is provided with a 238-inch internal diameter vessel and the core is built up of 648 fuel elements and 84 control rods. Each fuel bundle consists of 62 fuel rods and 2 water rods in an 8 x 8 array. The rated power of the Leibstadt BWR is 3012 MWt and it is designed for a net power of 942 MWe. 2 - Description of test: The purpose of the test STP-2001 which occurred on 15 October 1984 was to demonstrate the capability of the Reactor Core Isolation Cooling (RCIC) system to maintain the reactor water level above level 1 (-337 cm) following a total loss of feedwater with the HPCS system unavailable. The test was initiated by tripping the two operating feedwater pumps. The HPCS was prevented from initiating automatically. 3 - Experimental limitations or shortcomings: Plant description information is limited due to proprietary nature of plant design
Availability note (English)
Available on-line: http://www.nea.fr/abs/html/csni0004.htmlAdditional details
Identifiers
Publishing Information
- Imprint Pagination
- [html]
INIS
- Country of Publication
- Nuclear Energy Agency of the OECD (NEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 40013833
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- BWR TYPE REACTORS; CONTAINMENT SYSTEMS; CONTROL ELEMENTS; FEEDWATER; FUEL ELEMENT CLUSTERS; FUEL RODS; NUCLEAR POWER PLANTS; RCIC SYSTEMS; TEST FACILITIES; WEBSITES
- Descriptors DEC
- CONTAINMENT; COOLING SYSTEMS; DOCUMENT TYPES; ENERGY SYSTEMS; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; FUEL ASSEMBLIES; FUEL ELEMENTS; HYDROGEN COMPOUNDS; NUCLEAR FACILITIES; OXYGEN COMPOUNDS; POWER PLANTS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 1 ref.