Comparison of the MAAP4 code with the station blackout simulation in the IIST facility
Creators
- 1. Fauske and Associates, 16W070 West 83rd Street, Burr Ridge, IL 60527 (United States)
Description
Full text of publication follows: The Modular Accident Analysis Program (MAAP) is an integral system model to assess challenges to the reactor core, Reactor Coolant System (RCS) and containment for accident conditions. MAAP4 is the current version used by the MAAP Users Group to assess the responses to a spectrum of accident conditions. Benchmarking of the MAAP code with integral system experiments has been a continuing effort by MAAP developers and users. Several of these have been configured into dynamic benchmarks and are included in Volume III (Benchmarking) of the MAAP4 Users Manual (EPRI, 2004). One such integral experiment is the INER integral system test (IIST) constructed at the Institute of Nuclear Energy Research in Taiwan. This experimental facility is a reduced height, reduced pressure representation of a 3-loop PWR and has been used to examine several different types of accident sequences. One of these is a station blackout simulation with loss of auxiliary feedwater at the time that the transient is initiated. This is an important integral experiment to be compared with the MAAP4 code models. A parameter file (those values representing the system design and boundary experimental conditions) has been developed for the IIST facility and an input deck has been configured to represent a station blackout sequence with instantaneous loss of auxiliary feedwater. Of importance in this benchmark is (a) the rate at which the secondary side inventory is depleted, (b) the depletion of water within the reactor pressure vessel and (c) the time at which the top of the reactor core is uncovered. Comparisons have been made with these three different intervals and there is good agreement between the timing of these events for the MAAP4 benchmark. This is important since this reference sequence represents a set of boundary conditions that is continually with subsequent analyses being perturbations on this type of accident sequence. The good agreement between MAAP4 and the IIST presents a sound basis to examine the baseline sequence and such perturbations. Furthermore, since the station blackout has also been compared to RELAP5/MOD3 (Ferng et al., 1996), this provides a basis of comparison between MAAP and the previous calculation. REFERENCE: EPRI, 2004, 'MAAP4 Users Manual, Report prepared by Fauske and Associates for EPRI. Ferng, Y-M, et al., 1996, 'RELAP/MOD3 Simulation of the Station Blackout Experiment Conducted at the IIST Facility', Nuclear Technology, Vol. 116, pp. 66-77. (authors)
Availability note (English)
Available in abstract form only, full text entered in this recordAdditional details
Publishing Information
- Imprint Pagination
- 1 p.
- Report number
- INIS-FR--3960
Conference
- Title
- Nureth 11, eleventh international topical meeting on nuclear reactor thermal hydraulics
- Dates
- 2-6 Oct 2005
- Place
- Avignon (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 37001566
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- AUXILIARY WATER SYSTEMS; BENCHMARKS; COMPUTERIZED SIMULATION; LOSS OF COOLANT; M CODES; PRESSURE VESSELS; PWR TYPE REACTORS; TEST FACILITIES
- Descriptors DEC
- ACCIDENTS; AUXILIARY SYSTEMS; COMPUTER CODES; CONTAINERS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 2 refs.