Evaluation of JRC source term methodology using MAAP5 as a fast-running crisis tool for a BWR4 Mark I reactor
Creators
Description
JRC participated in the OECD/NEA FASTRUN benchmark reviewing fast-running software tools to model fission product releases during accidents at nuclear power plants. The main goal of fast-running software tools is to foresee the accident progression, so that mitigating actions can be taken and the population can be adequately protected. Within the FASTRUN, JRC used the MAAP 4.0.8 code and developed a methodology to obtain the source term (as activity released per radioisotope) of PWR and BWR station black-out accident scenarios. The modifications made in the MAAP models were limited to a minimum number of important parameters. This aims at reproducing a crisis situation with a limited time to adapt a generic input deck. This paper presents further studies, where JRC analysed the FASTRUN BWR scenario using MAAP 5.0.2 that has the capability of calculating doses. A sensitivity study was performed with the MAAP 5.0.2 DOSE package deactivated, using the same methodology as in the case of MAAP 4.0.8 for source term calculation. The results were close to the reference LTSBO SOARCA case, independently of the methodology used. One of the benefits of using the MAAP code is the short runtime of the simulations.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.anucene.2016.06.040Additional details
Identifiers
- DOI
- 10.1016/j.anucene.2016.06.040;
- PII
- S0306-4549(16)30484-4;
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 96
- Journal Page Range
- p. 446-454
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 47125378
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ACCIDENT MANAGEMENT; BENCHMARKS; BWR TYPE REACTORS; COOLANTS; ECCS; EPRI; FISSION PRODUCT RELEASE; FISSION PRODUCTS; M CODES; NUCLEAR POWER PLANTS; OUTAGES; PWR TYPE REACTORS; RCIC SYSTEMS; REACTOR ACCIDENTS; REACTOR CORES; REACTOR SAFETY; RELIEF VALVES; RISK ASSESSMENT; SENSITIVITY ANALYSIS; STEAM GENERATORS
- Descriptors DEC
- ACCIDENTS; BOILERS; COMPUTER CODES; CONTROL EQUIPMENT; COOLING SYSTEMS; ENERGY SYSTEMS; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; EQUIPMENT; FLOW REGULATORS; ISOTOPES; MANAGEMENT; MATERIALS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; RADIOACTIVE MATERIALS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR PROTECTION SYSTEMS; REACTORS; SAFETY; THERMAL POWER PLANTS; THERMAL REACTORS; VALVES; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- Copyright (c) 2016 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.