Modelling of HTR Confinement Behaviour during Accidents Involving Breach of the Helium Pressure Boundary
- 1. Unit of Nuclear Safety Research, CIEMAT, Avenida Complutense, 22 28040 Madrid (Spain)
- 2. Pebble Bed Modular Reactor (Pty) Limited, 1279 Mike Crawford Avenue, 0046 Centurion (South Africa)
Description
Development of HTRs requires the performance of a thorough safety study, which includes accident analyses. Confinement building performance is a key element of the system since the behaviour of aerosol and attached fission products within the building is of an utmost relevance in terms of the potential source term to the environment. This paper explores the available simulation capabilities (ASTEC and CONTAIN codes) and illustrates the performance of a postulated HTR vented confinement under prototypical accident conditions by a scoping study based on two accident sequences characterized by Helium Pressure Boundary breaches, a small and a large break. The results obtained indicate that both codes predict very similar thermal-hydraulic responses of the confinement both in magnitude and timing. As for the aerosol behaviour, both codes predict that most of the inventory coming into the confinement is eventually depleted on the walls and only about 1% of the aerosol dust is released to the environment. The cross comparison of codes states that largest differences are in the inter compartmental flows and the in-compartment gas composition.
Additional details
Publishing Information
- Journal Title
- Science and Technology of Nuclear Installations (Print)
- Journal Issue
- V. 2009(2009
- Journal Page Range
- p. 11
- ISSN
- 1687-6075
INIS
- Country of Publication
- Egypt
- Country of Input or Organization
- Egypt
- INIS RN
- 41034118
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- AEROSOL MONITORING; BOUNDARY ELEMENT METHOD; FISSION PRODUCTS; HELIUM COOLED REACTORS; HTR REACTOR; REACTOR ACCIDENT SIMULATION; SAFETY ANALYSIS; THERMAL HYDRAULICS
- Descriptors DEC
- AIR POLLUTION MONITORING; CALCULATION METHODS; ENRICHED URANIUM REACTORS; FINITE ELEMENT METHOD; FLUID MECHANICS; GAS COOLED REACTORS; HYDRAULICS; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; ISOTOPES; MATERIALS; MATHEMATICAL SOLUTIONS; MECHANICS; MONITORING; NUMERICAL SOLUTION; POOL TYPE REACTORS; RADIOACTIVE MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SIMULATION; THERMAL REACTORS; TRAINING REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS