United States Nuclear Regulatory Commission - Protecting People and the Environment

Simulation of a Station Black-Out in a PWR Under Midloop Conditions Using RELAP5/MOD3.2 (NUREG/IA-0173)

On this page:

Download complete document

Publication Information

Date Published: February 2000

Prepared by:
S. Martorell, S. Carlos, G. Verdú, V. Serradell, J. Rodenas, R. Miró, C. Llopis*

*C.N. Vandellos II
Travessera de les Corts, 55, Lateral
08028 Barcelona

Department of Chemical and Nuclear Engineering
Polytechnic University of Valencia
Camino de Vera, 14
Spain

Prepared as part of:
The Agreement on Research Participation and Technical Exchange
under the International Code Application and Maintenance Program (CAMP)

Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001

Availability Notice

Abstract

The present study consists of the simulation of a station black-out (SBO) transient, when the plant is in mid-loop conditions, using the thermal-hydraulic code RELAP5/MOD3.2.

This transient has been simulated on a typical three loop, Westinghouse design, pressurized water reactor (PWR) model working under mid-loop conditions.

The study was focused on obtaining the most important thermal-hydraulic variables in order to check the validity of the success criteria described in the plant probabilistic safety analysis (PSA), and also to analyze the code capability to simulate such conditions.

As a result of this study, it can be concluded that the main thermal-hydraulic plant features follow what it is foreseen in the plant PSA, although the values that are reached can not be completely taken as the correct ones due to the lack of experimental data to validate RELAP5 under these conditions.

Page Last Reviewed/Updated Friday, December 06, 2013