Report a Safety Concern
Search

The U.S. Nuclear Regulatory Commission is in the process of rescinding or revising guidance and policies posted on this webpage in accordance with Executive Order 14151 Ending Radical and Wasteful Government DEI Programs and Preferencing, and Executive Order 14168 Defending Women From Gender Ideology Extremism and Restoring Biological Truth to the Federal Government. In the interim, any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

Home NRC Library Document Collections NUREG-Series Publications Publications Resulting from International Agreements

Investigations of the VVER-1000 Coolant Transient Benchmark I with the Coupled Code System RELAP5/PARCS (NUREG/IA-0217)

On this page:

Download complete document

Publication Information

Date Published: December 2009

Prepared by:
V. Sánchez-Espinoza
Forschungszentrum Karlsruhe GmbH
Hermann-von-Helmholtz-Platz 1
76344 Eggenstein-Leopoldshafen
Germany

A. Calvo, NRC Project Manager

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

Availability Notice

Abstract

This report presents the investigations performed to validate the coupled code RELAP5/PARCS using data of a pump restart-up test carried out at the Kozloduy nuclear power plant (KNPP). An integral plant model—including the relevant primary and secondary systems as well as a detailed model of the reactor pressure vessel and of the core—was developed for RELAP5 and PARCS to simulate the pump restart-up test. From the comparison of the thermal-hydraulic data obtained during the tests with the code's predictions, it can be stated that the overall trends of most plant parameters are in a reasonable agreement with the experimental data. The investigations have shown some limitations of 1D thermal-hydraulic coarse models of the downcomer, lower, and upper plenum. Hence, multidimensional thermal-hydraulic models are needed for a more realistic description of the coolant mixing phenomena within the reactor pressure vessel.

Page Last Reviewed/Updated Tuesday, March 09, 2021