Published 2014 | Version v1
Miscellaneous Metadata-only

A stochastic-deterministic approach for evaluation of uncertainty in the predicted maximum fuel bundle enthalpy in a CANDU postulated LBLOCA event

Creators

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

Description

A stochastic-deterministic approach based on representation of uncertainties by subjective probabilities is proposed for evaluation of bounding values of functional failure probability and assessment of probabilistic safety margins. The approach is designed for screening and limited independent review verification. Its application is illustrated for a postulated generic CANDU LBLOCA and evaluation of the possibility distribution function of maximum bundle enthalpy considering the reactor physics part of LBLOCA power pulse simulation only. The computer codes HELIOS and NESTLE-CANDU were used in a stochastic procedure driven by the computer code DAKOTA to simulate the LBLOCA power pulse using combinations of core neutronic characteristics randomly generated from postulated subjective probability distributions with deterministic constraints and fixed transient bundle-wise thermal hydraulic conditions. With this information, a bounding estimate of functional failure probability using the limit for the maximum fuel bundle enthalpy can be derived for use in evaluation of core damage frequency. (author)

Part of:
PBNC 2014 : 19th Pacific Basin Nuclear Conference; 38th Annual Student Conference of the Canadian Nuclear Society and Canadian Nuclear Association

Additional details

Publishing Information

Publisher
Canadian Nuclear Society
Imprint Place
Toronto, Ontario (Canada)
ISBN
978-1-926773-16-2
Imprint Title
PBNC 2014 : 19th Pacific Basin Nuclear Conference; 38th Annual Student Conference of the Canadian Nuclear Society and Canadian Nuclear Association
Imprint Pagination
270 Megabytes
Journal Page Range
[15 p.]

Conference

Title
19. Pacific Basin Nuclear Conference; 38. Annual Student Conference of the Canadian Nuclear Society and Canadian Nuclear Association
Dates
24-28 Aug 2014
Place
Vancouver, British Columbia (Canada)

INIS

Country of Publication
Canada
Country of Input or Organization
Canada
INIS RN
49016229
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
CANDU TYPE REACTORS; COMPUTERIZED SIMULATION; LBLOCA; PROBABILISTIC ESTIMATION; RISK ASSESSMENT; SAFETY MARGINS
Descriptors DEC
ACCIDENTS; CALCULATION METHODS; HEAVY WATER MODERATED REACTORS; LOSS OF COOLANT; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR ACCIDENTS; REACTORS; SIMULATION; THERMAL REACTORS

Optional Information

Notes
Paper PBNC2014-319. 15 refs., 1 tab., 8 figs.