Published 2011 | Version v1
Miscellaneous Open

Use of RMPS to assess the reliability of Passive Safety Systems in CAREM-like reactor, past and present experiences. Second progress report

  • 1. Nuclear Safety Group - Centro Atómico Bariloche, CNEA (Argentina)

Description

Conclusions: • RMPS is being used successfully to assess the fulfillment of design criteria from a probabilistic point of view, in case of LOHS and LOCA, considering uncertainties in the reactor, in the passive safety systems and in the models as well. • Allows to quantify the probability of Event Tree headers related to some systems whose demand depends on the accidental sequence evolution (i.e. probability to demand a safety valve in case of a LOHS with success of the PRHRS, but working under deteriorated conditions). • Functional reliability quantification not already used in CAREM PSA, (Fault Trees or in Event Trees?)

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Part of:
Third (3rd) Research Coordination Meeting of the CRP on Development of Methodologies for the Assessment of Passive Safety System Performance in Advanced Reactors. Presentations

Additional details

Publishing Information

Imprint Title
Third (3rd) Research Coordination Meeting of the CRP on Development of Methodologies for the Assessment of Passive Safety System Performance in Advanced Reactors. Presentations
Imprint Pagination
vp.
Journal Page Range
63 p.
Report number
INIS-XA--14M1786

Conference

Title
3. Research Coordination Meeting of the CRP on Development of Methodologies for the Assessment of Passive Safety System Performance in Advanced Reactors
Dates
26-28 Apr 2011
Place
Vienna (Austria)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
46037577
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Progress Report
Descriptors DEI
FAULT TREE ANALYSIS; LOSS OF COOLANT; PROGRESS REPORT; REACTOR SAFETY; RELIABILITY; RELIEF VALVES
Descriptors DEC
ACCIDENTS; CONTROL EQUIPMENT; DOCUMENT TYPES; EQUIPMENT; FLOW REGULATORS; REACTOR ACCIDENTS; SAFETY; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; VALVES

Optional Information

Contract/Grant/Project number
Contract IAEA RC-15048-R0-2010