Published 2015 | Version v1
Book

Estimation of large early release frequency for Advanced Heavy Water Reactor

  • 1. Reactor Safety Division, Bhabha Atomic Research Centre, Mumbai (India)

Description

Level 2 probabilistic safety assessment (PSA) examines severe accidents through a combination of probabilistic and deterministic approaches, in order to determine the release of radionuclides from containment, including the physical processes that are involved in the loss of structural integrity of the reactor core. The probabilistic part focuses on the reliability evaluation of containment systems and the deterministic part focuses on the analysis of the physical processes of an accident (timing and magnitude of radioactivity release), and the response of the containment. The important tasks involved are: (i) grouping and categorization of accident sequences into plant damage states (PDSs) (ii) development of a containment event trees (CETs) (iii) development of CET top event definitions and quantification of failure probabilities, and (iv) assigning the release categories and estimation of large early release frequency (LERF). LERF is defined as the frequency of those accidents leading to rapid, unmitigated release of airborne fission products from the containment to the environment occurring before the effective implementation of offsite emergency response and protective actions such that there is the potential for early health effects. Such accidents generally include unscrubbed releases associated with early containment failure shortly after vessel breach, containment bypass events, and loss of containment isolation. Preliminary assessment of LERF, based on release categorization from qualitative expert judgement, has been carried out and the estimated LERF is found to be 1e-13/yr. The dominant contributors are: (a) LB LOCA with the failure of prompt shutdown coupled with containment isolation failure, (b) containment bypass event from main steam line break outside containment coupled with failure of main steam isolation valves, and (c) LB LOCA with complete failure of emergency core cooling system (ECCS) and loss of moderator cooling

Part of:
Proceedings of the international thorium energy conference: gateway to thorium energy

Additional details

Publishing Information

Publisher
Bhabha Atomic Research Centre
Imprint Place
Mumbai (India)
Imprint Title
Proceedings of the international thorium energy conference: gateway to thorium energy
Imprint Pagination
[637 p.]
Journal Page Range
2 p.

Conference

Title
international thorium energy conference: gateway to thorium energy
Acronym
ThEC15
Dates
12-15 Oct 2015
Place
Mumbai (India)

INIS

Country of Publication
India
Country of Input or Organization
India
INIS RN
47073981
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CONTAINMENT; FISSION PRODUCT RELEASE; HWLWR TYPE REACTORS; LOSS OF COOLANT; PROBABILISTIC ESTIMATION; REACTOR CORES; RISK ASSESSMENT
Descriptors DEC
ACCIDENTS; CALCULATION METHODS; HEAVY WATER MODERATED REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; WATER COOLED REACTORS

Optional Information

Notes
4 refs., 2 figs.