Published May 2000
| Version v1
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Primary coolant circuit coastdown and thermosyphon mode under failure of forced circulation in Indian PHWR
Creators
- 1. Reactor Safety Analysis Group, Nuclear Power Corporation, Mumbai (India)
Description
In Pressurised Heavy Water Reactor, in the absence of forced circulation in the Primary Cooling Circuit, the decay heat is removed by thermosyphoning. Accuracy in the prediction of thermosyphoning flow depends on the pressure drop model at low flow conditions. Behaviour of the plant under such condition is analysed using a transient analysis computer code 'ATMIKA.T'. Here, the analysis predicts thermosyphoning behaviour and compares with the plant transient data. Effect of different pressure drop models on the core flow is also studied. (author)
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Additional details
Publishing Information
- Imprint Title
- Experimental tests and qualification of analytical methods to address thermohydraulic phenomena in advanced water cooled reactors. Proceedings of a technical committee meeting
- Imprint Pagination
- 475 p.
- Journal Page Range
- p. 391-400
- ISSN
- 1011-4289
- Report number
- IAEA-TECDOC--1149
Conference
- Title
- Technical committee meeting on experimental tests and qualification of analytical methods to address thermohydraulic phenomena in advanced water cooled reactors
- Dates
- 14-17 Sep 1998
- Place
- Villigen (Switzerland)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 31031675
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- A CODES; AFTER-HEAT REMOVAL; FAILURES; FORCED CONVECTION; PHWR TYPE REACTORS; PRESSURE DROP; PRIMARY COOLANT CIRCUITS; THERMOSYPHON EFFECT; TRANSIENTS
- Descriptors DEC
- COMPUTER CODES; CONVECTION; COOLING SYSTEMS; ENERGY SYSTEMS; ENERGY TRANSFER; HEAT TRANSFER; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; MASS TRANSFER; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; REMOVAL
Optional Information
- Notes
- 3 refs, 7 figs