Published 2018 | Version v1
Miscellaneous

Treatment of modelling uncertainties for deterministic safety analysis

Creators

  • 1. Canadian Nuclear Safety Commission, Ottawa, Ontario (Canada)

Description

Treatment of modelling uncertainties is a generic issue related to quantifying margins from a safety analysis and obtaining confidence in safety conclusions drawn from the safety analysis. This issue is particularly important for analysis of design-basis accidents (DBAs). It is believed that the limit-of-operating envelope (LOE) methodology (i.e., setting the key operating parameters at their limiting values) is conservative so that the effects of modelling uncertainties are compensated by the LOE approach. This belief has been confirmed by an integrated best-estimate and uncertainty (BEAU) analysis for some transients such as the first 5-s power pulse transient in a large-break loss-of-coolant accident (LOCA), during which a large number of operating parameters play a dominant role in the simulation of the transient. However, this belief cannot be generalized and may not be true for other transients, especially for those (e.g., a loss-of-fueling-machine cooling accident) where there are only one or two operating parameters and the calculation results are predominantly affected by many modelling parameters. The presentation will discuss the relevant requirements stipulated in CNSC document REGDOC-2.4.1, Deterministic Safety Analysis, particularly the need for an explicit treatment of modelling uncertainties, even when the LOE methodology is used in a safety analysis for DBA. The presentation will also review the CANDU Owners' group report Guidelines for Application of the LOE/ROE Methodologies to Deterministic Safety Analysis (COG-11-9023 R01) and substantiate its applications. (author)

Availability note (English)

Available as a slide presentaton only.
Part of:
7th International workshop on CANDU safety association for sustainability (CANSAS-2018). International severe accident management conference (ISAMC 2018)

Additional details

Publishing Information

Publisher
Canadian Nuclear Safety Commission
Imprint Place
Ottawa, Ontario (Canada)
Imprint Title
7th International workshop on CANDU safety association for sustainability (CANSAS-2018). International severe accident management conference (ISAMC 2018)
Imprint Pagination
225 Megabytes
Journal Page Range
[24 p.]

Conference

Title
7. International Workshop on CANDU Safety Association for Sustainability; ISAMC 2018: International Severe Accident Management Conference
Acronym
CANSAS-2018
Dates
15-18 Oct 2018
Place
Ottawa, Ontario (Canada)

INIS

Country of Publication
Canada
Country of Input or Organization
Canada
INIS RN
51015955
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
CANDU TYPE REACTORS; DATA COVARIANCES; DETERMINISTIC ESTIMATION; REACTOR ACCIDENTS; RISK ASSESSMENT; SAFETY ANALYSIS; SIMULATION
Descriptors DEC
ACCIDENTS; CALCULATION METHODS; HEAVY WATER MODERATED REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; THERMAL REACTORS

Optional Information