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any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.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

Application of RELAP5/MOD3.1 to ATWS Analysis of Control Rod Withdrawal From 1% Power Level (NUREG/IA-0180)

On this page:

Download complete document

Publication Information

Date Published: June 2000

Prepared by:
H. Kantee
Fortum Engineering Ltd.
P.O. Box 10
00048 Fortum
FINLAND

Prepared as part of:
The Code Application and Maintenance Program (CAMP)

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

Availability Notice

Abstract

The RELAP5/MOD3.1 computer code has been applied in the analysis of a regulating control rod group withdrawal from 1 % power level. The analysis has been carried out as an Anticipated Transient Without Scram (ATWS) event.

The analysis is related to an extensive inherent boron dilution study which was performed to Loviisa Nuclear Power Plant (NPP) in the mid 1990's. The main goal of the analysis was to study if during the accident so called boiling-condensing mode develops and thereafter a water plug with low boron concentration is formed in the cold leg loop seal.

Page Last Reviewed/Updated Tuesday, March 09, 2021