Published 2002
| Version v1
Miscellaneous
Thermohydraulic analysis of loss of coolant accident (LOCA) in the RP-10 reactor
Creators
- 1. Instituto Peruano de Energia Nuclear, Lima (Peru). Departamento de Calculo Analisis y Seguridad
Description
The loss of coolant accident proposed is the rupture of the tangential tube that goes through the reactor walls in any part within the reactor pool, leaking water from the inner of the reactor tank through the ends of the tangential tube, connected to the exterior. From the thermohydraulic analysis performed it is concluded that in case there is no an Emergency Coolant Core System (ECCS), nuclear fuel elements would be melted; furthermore, the ECCS should act at least during 150,000 seconds to assure that coolant with tight air is enough to cool fuel elements
Additional details
Additional titles
- Original title (Spanish)
- Analisis termohidraulico del accidente de perdida de refrigerante (loss of coolant accident, LOCA) en el reactor RP-10
Publishing Information
- Imprint Place
- Lima (Peru)
- Imprint Title
- 1998-2001 Scientific Technological Report
- Imprint Pagination
- 512 p.
- Journal Page Range
- p. 174-177
- ISSN
- 1684-1662
- Report number
- INIS-PE--039
INIS
- Country of Publication
- Peru
- Country of Input or Organization
- Peru
- INIS RN
- 34083336
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ACCIDENTS; COOLING SYSTEMS; ECCS; FLUID FLOW; HYDRAULICS; LOSS OF COOLANT; REACTOR ACCIDENTS; REACTOR COOLING SYSTEMS; RP-10 REACTOR; THERMODYNAMICS
- Descriptors DEC
- ACCIDENTS; COOLING SYSTEMS; ENERGY SYSTEMS; ENGINEERED SAFETY SYSTEMS; FLUID MECHANICS; MECHANICS; POOL TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Imprint:Informe Cientifico Tecnologico 1998-2001