Preliminary use of RELAP5 Code with Internal Assessment of Uncertainty
Creators
- 1. Dipartimento di Costruzioni Meccaniche e Nucleari, University of Pisa, Pisa (Italy)
Description
The present work deals with the preliminary use of the RELAP5 code with the internal assessment of the uncertainty. The activity has been started as a follow up of the research leading to the proposal and applicability of UMAE (Uncertainty Methodology base on Accuracy Extrapolation) uncertainty methodology. The concept of hypercube to characterize the status of a LWR plant during any transient and the assumption of uncertainty connected with the hypercubes are adopted: the CIAU (Code with Internal Assessment of Uncertainty) method has been set up. In the frame of the activity of CIAU development, matrix and a vector for uncertainty have been obtained; three type of matrixes and vectors are utilized: 1. matrix and vector deriving from tests results qualified by UMAE conditions; 2. matrix and vector deriving from tests results obtained from several sources (UMAE et not UMAE qualified) 3. matrix and vector used only for testing purposes (not derived from a physical process) are derived to evaluate the uncertainty connected with a generic time trend calculated by the code. The present paper describes an application of matrix and vector at item 3. (author)
Additional details
Publishing Information
- Publisher
- Japan Society of Mechanical Engineers
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- ICONE-7: Proceedings of the 7th international conference on nuclear engineering
- Imprint Pagination
- 4252 p.
- Journal Page Range
- [10 p.]
Conference
- Title
- 7. international conference on nuclear engineering
- Acronym
- ICONE-7
- Dates
- 19-23 Apr 1999
- Place
- Tokyo (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 31009003
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FORECASTING; HYDRAULICS; NUCLEAR POWER PLANTS; R CODES; REACTOR ACCIDENTS; RELIABILITY; THERMODYNAMICS; VERIFICATION; WATER MODERATED REACTORS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; NUCLEAR FACILITIES; POWER PLANTS; REACTORS; THERMAL POWER PLANTS
Optional Information
- Notes
- This CD-ROM can be used for WINDOWS 95/98/NT, MACINTOSH and UNIX; Acrobat Reader 3.0.1 is included; Data in PDF format, Track No. 05, ICONE-7396