Published November 1989
| Version v1
Journal article
Pilot study for a plant code uncertainty method
Description
The purpose of this paper is to describe an approach to the calculation of uncertainty in code predictions of plant transients and to demonstrate part of it. For unbiased codes, this uncertainty must be assessed to provide useful advice to decision makers. The objective of the method described is to evaluate the uncertainty in code predictions in a way that is useful to decision makers. The decisions may concern either reactor safety issues (including the evaluation of licensing submissions) or selecting technical areas for research aimed at uncertainty reduction
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 60
- Series
- Trans. Am. Nucl. Soc.
- Journal Page Range
- 761
- ISSN
- 0003-018X
- CODEN
- TANSA
Conference
- Title
- Winter meeting of the American Nuclear Society (ANS) and nuclear power and technology exhibit.
- Dates
- 26-30 Nov 1989.
- Place
- San Francisco, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 22085622
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; COMPUTERIZED SIMULATION; HEAT TRANSFER; HYDRAULICS; INFORMATION NEEDS; LOSS OF COOLANT; MANAGEMENT; PIPES; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; REACTOR LICENSING; REACTOR SAFETY; RESEARCH PROGRAMS; RUPTURES; T CODES; VOID FRACTION
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; COOLING SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FAILURES; LICENSING; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SAFETY; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-891103--.