Evaluation of the Impact That PARs Have on the Hydrogen Risk in the Reactor Containment: Methodology and Application to PSA Level 2
- 1. Service d'évaluation des Accidents Graves et des rejets Radioactifs, Institut de Radioprotection et de Sûreté Nucléaire, Direction de la Sûreté des Réacteurs, BP 17, 92262 Fontenay aux Roses, France
Description
This paper presents a methodology and its application to a Level 2 Probabilistic Safety Assessment (PSA-2), to evaluate the impact of the Passive Autocatalytic Recombiners (PARs) on the hydrogen risk in the reactor containment in case of a severe accident. Among the whole set of accidental scenarios calculated in the framework of the PSA-2, nine have been selected as representative in terms of the in-vessel hydrogen production rate and in-vessel total produced hydrogen mass. Five complementary scenarios have been added as representative of the core reflooding situations. For this set of selected scenarios the evolution of the conditions in the containment (i.e., pressure, temperature, and composition) during the in-vessel phase of the accident has been evaluated by means of a lumped parameter approach. The use of spray systems in the containment has also been considered as well as the presence of recombiners. Moreover, the ignition by recombiners of the flammable atmosphere has been considered.
Files
10.1155_2010_320396.pdf
Files
(457.0 kB)
| Name | Size | Download all |
|---|---|---|
|
md5:98868a1f5a89de75875c3ffaf6dae8a2
|
457.0 kB | Preview Download |
System files
(25.2 kB)
| Name | Size | Download all |
|---|
Additional details
Identifiers
- DOI
- 10.1155/2010/320396;
Publishing Information
- Journal Title
- Science and Technology of Nuclear Installations
- Journal Volume
- 2010
- Journal Page Range
- 1-7
- ISSN
- 1687-6075
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BEYOND-DESIGN-BASIS ACCIDENTS; CONTAINMENT; CONTAINMENT BUILDINGS; CONTAINMENT SYSTEMS EXPERIMENT; CORE FLOODING SYSTEMS; FLAMMABILITY; HYDROGEN; INTERSTITIAL HYDROGEN GENERATION; PRESSURE VESSELS; PROBABILISTIC ESTIMATION; REACTOR SAFETY; REACTOR VESSELS; RECOMBINERS; RISK ASSESSMENT; SAFETY ANALYSIS; SEVERE ACCIDENTS
- Descriptors DEC
- ACCIDENTS; BEYOND-DESIGN-BASIS ACCIDENTS; BUILDINGS; CALCULATION METHODS; COMBUSTION PROPERTIES; CONTAINERS; CONTAINMENT; ECCS; ELEMENTS; ENGINEERED SAFETY SYSTEMS; NONMETALS; PHYSICAL RADIATION EFFECTS; RADIATION EFFECTS; REACTOR PROTECTION SYSTEMS; REACTOR SAFETY EXPERIMENTS; SAFETY
Optional Information
- Copyright
- © Author(s)
- Notes
- Record automatically processed