Published 1999 | Version v1
Computer medium

Preliminary use of RELAP5 Code with Internal Assessment of Uncertainty

  • 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)

Part of:
ICONE-7: Proceedings of the 7th international conference on nuclear engineering

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