Published 2002 | Version v1
Miscellaneous

Thermohydraulic analysis of loss of coolant accident (LOCA) in the RP-10 reactor

  • 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

Part of:
1998-2001 Scientific Technological Report

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

Optional Information

Notes
Imprint:Informe Cientifico Tecnologico 1998-2001