Published May 2000 | Version v1
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Primary coolant circuit coastdown and thermosyphon mode under failure of forced circulation in Indian PHWR

  • 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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Experimental tests and qualification of analytical methods to address thermohydraulic phenomena in advanced water cooled reactors. Proceedings of a technical committee meeting

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