Pre- and post-test analysis of LOBI MOD2 Test ST-02 (BT-00) with RELAP5/MOD1 and MOD2 (loss of feed water)

Technical Report · Wed Apr 01 04:00:00 EST 1992

OSTI ID:10148173

Scriven, A H ^[1]

---

1. National Power, Leatherhead (United Kingdom)

The experiment ST-O2 (later renamed BT-00) is one of a series of Special Transient tests being performed on the electrically heated LOBI facility at Ispra in Italy. This test was designed to simulate a loss of main feedwater transient leading via a steam generator dryout to a long term cooldown using bleed and feed. The RELAP5/MOD2 code has been chosen by the Board for assessment work on the Sizewell Pre-Operation Safety Report. It was originally designed for Loss of Coolant Accidents, but is now finding wider applications. RELAP5/MOD2 was used for a pre-test calculation, and RELAP5/MOD2 for the detailed post-test analysis. This was to allow cross-code comparisons, assess the possibility of using RELAP5 for pressurized transients and because the final phase of bleed and feed which occurs in test ST02 is more representative of Small Break transients than Pressurized Faults. This report documents the results of this calculation and comparisons with the test data. After accounting for test conditions and events outside the original specification the RELAP5/MOD2 code was found to perform rather well.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (United States). Office of Nuclear Regulatory Research; National Power, Leatherhead (United Kingdom)
• Sponsoring Organization: Nuclear Regulatory Commission, Washington, DC (United States)
• OSTI ID: 10148173
• Report Number(s): NUREG/IA--0061; PWR/HTWG/P--(87)562; ON: TI92014255; IN: TPRD/L/ES0754/M87
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900
99 GENERAL AND MISCELLANEOUS
990200
COMPUTER CALCULATIONS
COMPUTER PROGRAM DOCUMENTATION
COMPUTERIZED SIMULATION
DRYOUT
FEEDWATER
INTERNATIONAL COOPERATION
LOSS OF COOLANT
MATHEMATICS AND COMPUTERS
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
PWR TYPE REACTORS
R CODES
REACTOR SAFETY
RESEARCH PROGRAMS
SIZEWELL-B REACTOR
STEAM GENERATORS
TRANSIENTS