Published 1988 | Version v1
Book

Dryout heat flux in debris beds with different size particles

  • 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan)

Description

In the event of a severe LWR accident, degraded core materials would form a debris bed which would continue to release decay heat. In order to mitigate such an accident within the reactor vessel, it is important to estimate the coolability of the debris bed. This can be determined from the dryout heat flux and depends on many parameters such as the configuration of the debris bed and the coolant flow conditions. In the present study, the pressure drop and dryout heat flux in a debris bed with mixed particles were measured and empirical correlations for permeabilities for laminar and turbulent flow were developed. The correlations were applied to an analytical model to predict dryout heat flux. The following conclusions were drawn: (1) the dryout heat flux decreases when smaller particles are mixed with larger particles; and (2) the analytical model gives reasonable agreement with the measured dryout heat flux when the mass fraction of small diameter particles is less than 0.3. (author). Poster presentation. 6 refs, 5 figs

Part of:
Severe accidents in nuclear power plants. V.2

Additional details

Publishing Information

Publisher
IAEA.
Imprint Place
Vienna (Austria)
ISBN
92-0-020288-8
Imprint Title
Severe accidents in nuclear power plants
Imprint Pagination
772 p.
Series
Proceedings series.
Journal Page Range
v. 2 p. 431-438.

Conference

Title
International symposium on severe accidents in nuclear power plants.
Dates
21-25 Mar 1988.
Place
Sorrento (Italy).

INIS

Country of Publication
Austria
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
20034882
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
AFTER-HEAT REMOVAL; COMPUTERIZED SIMULATION; CORIUM; HEAT FLUX; HEAT TRANSFER; MELTDOWN; PARTICLE SIZE; POWER REACTORS; REACTOR CORES; VERIFICATION
Descriptors DEC
ACCIDENTS; ENERGY TRANSFER; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SIMULATION; SIZE

Optional Information

Secondary number(s)
IAEA-SM--296/59P.