Published 2015 | Version v1
Book

Design feasibility study on corium stabilization in bottom end-fitting for AHWR under accident condition

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

Description

Advanced Heavy Water Reactor (AHWR) is being designed in a robust way to cater both Design and Beyond Design Basis Accidents to meet all the safety functions. All the functions are met by passive means with special emphasis on 'residual heat removal' which is catered by passive natural circulation mode. In context to Design Basis Accidents, several features are designed to handle worst kind of scenario like Station Black Out. For Design Extension Conditions (DEC), the means of passive natural circulation is adopted as a design means to meet the DEC-A conditions like cooling of moderator by natural circulation means with GDWP inventory. Under the DEC-B condition where large scale of fuel melting is envisaged, a core catcher is designed with active/passive cooling modes to take care of the residual heat of the core. All the mentioned features utilizes the natural mode of heat transfer to meet one of the safety function i.e. 'residual heat removal'. The analysis shows that the tube sheet as well as lattice tube temperatures remain low and are able to take out the heat from corium through sub-cooled nucleate boiling. The ES cooling is sufficient to maintain the cooling water in subcooled condition. The integrity of tube sheet and lattice tube is maintained

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
47073967
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
AFTER-HEAT REMOVAL; CORIUM; DESIGN BASIS ACCIDENTS; HWLWR TYPE REACTORS; REACTOR COOLING SYSTEMS; REACTOR SAFETY
Descriptors DEC
ACCIDENTS; COOLING SYSTEMS; ENERGY SYSTEMS; HEAVY WATER MODERATED REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; REMOVAL; SAFETY; WATER COOLED REACTORS

Optional Information

Notes
4 figs., 2 refs.