VVER-440 Containment Thermal Hydraulic Analyses With MELCOR and CONTAIN Codes

Conference · Mon Jul 01 00:00:00 EDT 2002

OSTI ID:21070105

Gromov, Gregory; Lola, Igor; Sholomitsky, Stanislav; Gumenyuk, Dmitry; Shikhabutinov, Valery; Alekseev, Yury ^[1]; Wagner, K C ^[2]; Dallman, Jack ^[3]

---

1. Energorisk Ltd., vul. Radgospna 35-37, Room 707, Kyiv, 252142 (Ukraine)
2. Scientech Inc. (United States)
3. Los Alamos National Laboratory, Nuclear Design and Risk Analysis Group (D-5), Los Alamos, NM 87545 (United States)

In support of the analyses for the Rivne Nuclear Power Plant (RNPP) VVER-440/213 (Ukraine) Safety Analysis Report (SAR), detailed MELCOR and CONTAIN models of the containment were developed. The RNPP containment features a bubble condenser tower with air locks and active and passive spray systems. Code input models were developed to accurately represent the containment volumes, room interconnections, structural masses, and the engineering safety features. Although MELCOR 1.8.3 was the primary tool for the SAR containment analysis, comparison calculations were performed using CONTAIN Version 1.12. Consequently, both the response of the VVER-440 containment to limiting design conditions as well as a comparison of the two codes is presented. In the context of SAR requirements, the present application was performed for design basis accidents with conservative assumptions to compare the containment temperature and pressure with design criteria. The peak containment pressure and temperature were evaluated using the most intensive release of the primary and secondary coolant into the hermetic compartments, in particular, for the large break loss of coolant accident and main steam line break. Conservative coolant release data were evaluated using the RELAP5/Mod3.2 SAR model. The selection of the accident scenario, initial and boundary conditions, and the major results are presented. The results of the analyses will be included in the design basis accident analysis chapter of the RNPP SAR. (authors)

• Research Organization: The ASME Foundation, Inc., Three Park Avenue, New York, NY 10016-5990 (United States)
• OSTI ID: 21070105
• Resource Relation: Conference: 10. international conference on nuclear engineering - ICONE 10, Arlington - Virginia (United States), 14-18 Apr 2002; Other Information: Country of input: France
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
AIR
COMPARATIVE EVALUATIONS
CONTAINMENT
COOLANTS
DESIGN
DESIGN BASIS ACCIDENTS
LOSS OF COOLANT
NUCLEAR POWER PLANTS
REACTOR SAFETY
SAFETY ANALYSIS
STEAM LINES
THERMAL HYDRAULICS
UKRAINE
WWER TYPE REACTORS