Published 1992 | Version v1
Report Restricted

RCS pressure under reduced inventory conditions following a loss of residual heat removal

Creators

Description

The thermal-hydraulic response of a closed-reactor coolant system to loss of residual heat removal (RHR) cooling is investigated. The processes examined include: core coolant boiling and steam generator reflux condensation, pressure increase on the primary side, heat transfer mechanisms on the steam generator primary and secondary sides, and effects of noncondensible gas on heat transfer processes

Availability note (English)

MF available from INIS under the Report Number; OSTI as DE92017919; NTIS; INIS; US Govt. Printing Office Dep.

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Additional details

Publishing Information

Imprint Pagination
9 p.
Report number
EGG-M--91507

Conference

Title
American Society of Mechanical Engineers national heat transfer conference and exposition.
Dates
9-12 Aug 1992.
Place
San Diego, CA (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
23083567
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
AFTER-HEAT REMOVAL; COOLING; HEAT TRANSFER; HYDRAULICS; MATHEMATICAL MODELS; NOZZLES; PRESSURIZERS; PWR TYPE REACTORS; REACTOR COOLING SYSTEMS; REACTOR SAFETY; STEAM GENERATORS
Descriptors DEC
BOILERS; COOLING SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; REMOVAL; SAFETY; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Contract/Grant/Project number
Contract AC07-76ID01570
Funding organization
Nuclear Regulatory Commission, Washington, DC (United States).
Secondary number(s)
CONF-920804--21.