Published May 23, 2001 | Version v1
Report

Validation of the CFX-4 Code for PWR Fault Analysis

  • 1. AEA Technology pic, A32 Winfrith, Dorchester, Dorset, DT2 8DH (United Kingdom)

Description

This paper presents the current status of the AEA Technology work validating CFX-4 as a tool for modelling fluid transport and mixing in reactor coolant systems. Conclusions are given on the adequacy of this methodology for correctly predicting turbulent mixing in the fault transients of relevance. CFX-4 code predictions have been carried out against pump start-up data from the 1/5 scaled (based on Ringhals) experiments at Vattenfall. These experiments are concerned with the transport of a boron depleted slug of fluid from the cold leg to the vessel. These computational results showed the timescales and concentration of the boron depleted slug reaching the core region to be well predicted. AEA Technology, on behalf of UK Health and Safety Executive, is also participating in the pump start-up ISP at the University of Maryland during 1999/2000. Predictions of thermal mixing have been carried out against Sizewell-B plant data from Emergency Boration System (EBS) commissioning tests. These data provide a stringent test for the code which successfully replicated the broad features but failed to reproduce an observed swirl. This modelling discrepancy is currently under investigation. (authors)

Part of:
Proceedings of the workshop on advanced thermal-hydraulic and neutronic codes: current and future applications

Additional details

Publishing Information

Imprint Title
Proceedings of the workshop on advanced thermal-hydraulic and neutronic codes: current and future applications
Imprint Pagination
723 p.
Journal Page Range
p. 552-563
Report number
NEA-CSNI-R--2001-2

Conference

Title
current and future applications
Acronym
Workshop on advanced thermal-hydraulic and neutronic codes
Dates
10-13 Apr 2000
Place
Barcelona (Spain)

INIS

Country of Publication
Nuclear Energy Agency of the OECD (NEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
39036594
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ACCIDENTS; BORON; COMMISSIONING; CONTAINERS; FLUIDS; FORECASTING; MIXING; PUMPS; PWR TYPE REACTORS; REACTOR COOLING SYSTEMS; SAFETY; SIMULATION; START-UP; TRANSIENTS; VALIDATION
Descriptors DEC
COOLING SYSTEMS; ELEMENTS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; EQUIPMENT; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SEMIMETALS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
5 refs.