Published November 1990
| Version v1
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Passive decay heat removal by natural circulation
- 1. Bhabha Atomic Research Centre, Bombay (India)
Description
The standardised 235 MWe PHWRs being built in India are the pressure tube type, heavy water moderated, heavy water cooled and natural uranium fuelled reactors. Several passive safety features are incorporated in these reactors. These include: (1) Containment pressure reduction and fission product trapping with the help of suppression pool following LOCA. (2) Emergency coolant injection by means of accumulators. (3) Large heat sink provided by the low temperature moderator under accident conditions. (4) Low excess reactivity, through the use of natural uranium fuel and on power fuelling. (5) Residual heat removal by means of natural circulation, etc. of which the last item is the subject matter of this report. (author). 8 refs, 10 figs
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Additional details
Publishing Information
- Imprint Title
- Passive safety features in current and future water cooled reactors
- Imprint Pagination
- 162 p.
- Journal Page Range
- p. 57-64.
- Report number
- IWGATWR--3
Conference
- Title
- Technical committee on passive safety features in current and future water cooled reactors.
- Dates
- 21-24 Mar 1989.
- Place
- Moscow (USSR).
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 22016781
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT REMOVAL; CONTAINMENT SHELLS; CONTAINMENT SYSTEMS; NATURAL CONVECTION; PHWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COOLING SYSTEMS; REACTOR SAFETY
- Descriptors DEC
- ACCIDENTS; CONTAINMENT; CONVECTION; COOLING SYSTEMS; ENERGY TRANSFER; HEAT TRANSFER; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; REACTOR COMPONENTS; REACTORS; SAFETY