Published August 2002 | Version v1
Report

CAREM-25 accident analysis

  • 1. Comision Nacional de Energia Atomica, Centro Atomico Bariloche (Argentina)

Description

This paper describes the response of the CAREM reactor prototype, CAREM-25, and its safety systems to representative accidental initiating events. A nodalization of the primary circuit including the steam generators was developed for RELAP5 and RETRAN02 codes to perform the accident analysis. Also a simplified two zone non-equilibrium model was developed to calculate long term reactor behavior. Secondary Shutdown, Residual Heat Removal and Emergency Injection systems were also modeled in detail. The reactor steady state was calculated at full power. The results agree quite well with design values, and this condition was used as reference for the accident analysis. Several initiating events were considered for the accident analysis. They were grouped into Reactivity Insertion, Loss of Heat Sink (LOHS) and Loss of Coolant Accidents (LOCA). As there are no primary pumps, Total Loss of Flow Accident (LOFA) is not applicable in this case. Results show that the design requirements are verified and the reactor reaches a safe condition, without need of active intervention. As a general conclusion, it could be said, that due to the large coolant inventory in the primary circuit, the system has a large thermal inertia and long response time in the event of transients or severe accidents. (author)

Part of:
Small and medium sized reactors: Status and prospects. Proceedings

Additional details

Publishing Information

ISBN
92-0-114802-X
Imprint Title
Small and medium sized reactors: Status and prospects. Proceedings
Imprint Pagination
796 p.
Journal Issue
no. 14/P
Series
C and S papers series
Journal Page Range
p. 673-683
ISSN
1563-0153
Report number
IAEA-CSP--14/P

Conference

Title
Status and prospects
Acronym
International seminar on small and medium sized reactors
Dates
27-31 May 2001
Place
Cairo (Egypt)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
33045071
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
AFTER-HEAT REMOVAL; ENGINEERED SAFETY SYSTEMS; LOSS OF COOLANT; LOSS OF FLOW; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; R CODES; REACTIVITY INSERTIONS; REACTOR KINETICS; REACTOR SAFETY; REACTOR SHUTDOWN; TRANSIENTS
Descriptors DEC
ACCIDENTS; COMPUTER CODES; COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; KINETICS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; REMOVAL; SAFETY; SHUTDOWN; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Proposed descriptors and Free-text terms
CAREM REACTOR

Optional Information

Notes
4 refs, 8 figs, 4 tabs
Secondary number(s)
IAEA-SR--218/5