Published October 1986
| Version v1
Miscellaneous
Capabilities of system codes in simulating small break LOCAS in PWRS
Creators
- 1. Pisa Univ. (Italy). Dipt. di Costruzioni Meccaniche e Nucleari
Description
The capabilities of thermalhydraulic system codes in simulating SBLOCAs in PWRs is reviewed. The results of the participation of Pisa University in the CSNI - ISP 18, are presented. A 'first generation' and two 'advanced' codes have been utilized in pre- and post-test studies. In particular, the influence on the prediction of user experience, of uncertainties in boundary conditions, of code version and of nodalization are discussed
Additional details
Additional titles
- Augmented title (English)
- RELAP code
Publishing Information
- ISBN
- 0-919784-11-9
- Imprint Title
- Proceedings of the 2. international conference on simulation methods in nuclear engineering
- Imprint Pagination
- 950 p.
- Journal Page Range
- p. 928-950.
- Report number
- INIS-mf--12868(v.1,2)
Conference
- Title
- 2. International conference on simulation methods in nuclear engineering.
- Dates
- 14-16 Oct 1986.
- Place
- Montreal, PQ (Canada).
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 22063890
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPARATIVE EVALUATIONS; COMPUTERIZED SIMULATION; LOSS OF COOLANT; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; R CODES
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; COOLING SYSTEMS; ENRICHED URANIUM REACTORS; EVALUATION; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS