Natural circulation cooldown analysis for Korea next generation reactor (KNGR)

Book · Mon Jul 01 04:00:00 EDT 1996

OSTI ID:248182

Lee, S S; Kim, E K; Park, B H; Kim, Y H; Ko, D Y ^[1]

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1. Korea Atomic Energy Research Inst., Taejon (Korea, Republic of)

This paper is to determine if KNGR`s NSSS can be safely cooled and depressurized in accordance with the requirements of NRC Branch Technical Position (BTP) RSB 5-1 when the reactor coolant pumps are not available during design basis transients and accidents. NRC Standard Review Plan NUREG-0800, Section 5.4.7 requires compliance with BTP RSB 5-1. BTP RSB 5-1 in turn requires that a plant shall be capable of going from normal operating conditions to cold shutdown using only safety-grade systems and assuming a concurrent loss of offsite power and a single failure. In this paper, LTC (Long Term Code) code is used to analyze this phenomena. Reactor Coolant Gas Vent System (RCGVS) is used to depressurize RCS pressure. The single failure assumed for this paper is a failure of a diesel generator for initiation of the RCS depressurization. In the results, the KNGR`s NSSS shows the plant could be cooled and depressurized in accordance with RSB 5-1 using the RCGVS.

• OSTI ID: 248182
• Report Number(s): CONF-960306--; ISBN 0-7918-1226-X
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
AFTER-HEAT REMOVAL
AVAILABILITY
COMPUTERIZED SIMULATION
COOLING
DEPRESSURIZATION
DESIGN BASIS ACCIDENTS
ENGINEERED SAFETY SYSTEMS
L CODES
NATURAL CONVECTION
OUTAGES
PUMPS
PWR TYPE REACTORS
REACTOR COOLING SYSTEMS
REPUBLIC OF KOREA
THEORETICAL DATA
US NRC