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Simulation of ROSA-2 Test 3 Counterpart with TRACE5 – Application to Nuclear Power Plant (NUREG/IA-0512)

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Publication Information

Manuscript Completed: April 2018
Date Published: March 2019

Prepared by:
S. Gallardo, A. Querol, Lorduy, and G. Verdu

Universitat Politecnica de Valencia
Instituto Universitario de Seguridad Industrial, Radiofisica y Medioambiental
Cami de Vera s/n
46022 Valencia, SPAIN

Kirk Tien, NRC Project Manager

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

Prepared as part of
The Agreement on Research Participation and Technical Exchange
Under the Thermal-Hydraulic Code Applications and Maintenance Program (CAMP)

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

Availability Notice

Abstract

This paper presents a first approach of a hot leg Small Break Loss-Of-Coolant Accident (SBLOCA) application to a Nuclear Power Plant (NPP). For this purpose, a standard 3-loop PWR NPP model by means of the thermal-hydraulic code TRACE5 patch 2 and Symbolic Nuclear Analysis Packages (SNAP) has been used.

The SBLOCA transient corresponds to the Test 3 (SB-HL-18) conducted at the Large Scale Test Facility (LSTF) of the Japan Atomic Energy Agency (JAEA) in the frame of the OECD/NEA ROSA-2 Project. LSTF is a Full-Height Full-Pressure (FHFP) facility designed to simulate the Tsuruga unit II NPP (a 4-loop W-type PWR) with volume and power scaled by a factor of 1/48. Test 3 simulates a PWR 1.5% hot leg SBLOCA with an assumption of the total failure of High Pressure Injection (HPI) system under two different pressure conditions.

Considering the assumptions of this test, some modifications have been performed in the 3-loop PWR TRACE5 model. The simulation results are provided throughout several graphs where the main system variables, such as primary and secondary pressures, collapsed liquid levels and temperatures are shown.

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