Published 2013
| Version v1
Miscellaneous
Simulation of a low-pressure severe accident scenario in a PWR with ATHLET-CD
Creators
- 1. Bochum Univ. (Germany). Reactor Simulation and Safety Group
Description
The plant behavior of a Pressurized Water Reactor (PWR) during a severe accident scenario is analyzed with system code ATHLET-CD Mod. 2.2C in order to assess the code capabilities in terms of the late-phase of the core degradation. For this purpose a severe accident sequence caused by a Station Black-out and a large break in the primary cooling system is simulated both without any accident management measures and with a delayed reflooding of the substantially degraded core. Selected code results are presented in this paper. (orig.)
Additional details
Additional titles
- Original title (English)
- Jahrestagung Kerntechnik 2013. Dokumentation
Publishing Information
- Imprint Title
- Annual meeting on nuclear technology 2013. Documentation
- Imprint Pagination
- 1142 p.
- Journal Page Range
- 6 p.
Conference
- Title
- Annual meeting on nuclear technology 2013
- Original Conference Title
- Jahrestagung Kerntechnik 2013
- Dates
- 14-16 May 2013
- Place
- Berlin (Germany)
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 45049765
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- A CODES; ACCIDENT MANAGEMENT; DEPRESSURIZATION; ECCS; ELECTRICITY; LEAKS; LOSS OF COOLANT; MELTDOWN; POWER SUPPLIES; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; REACTOR ACCIDENT SIMULATION; REACTOR ACCIDENTS; REACTOR CORE DISRUPTION; RUPTURES; THERMAL HYDRAULICS; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; COOLING SYSTEMS; ELECTRONIC EQUIPMENT; ENERGY SYSTEMS; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; EQUIPMENT; FAILURES; FLUID MECHANICS; HYDRAULICS; MANAGEMENT; MECHANICS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR PROTECTION SYSTEMS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Imprint:Jahrestagung Kerntechnik 2013. Dokumentation