Published November 1985 | Version v1
Report Open

Hypothetical accident scenario analyses for a 250-MW(t) modular high temperature gas-cooled reactor

Description

This paper describes calculations performed to characterize the inherent safety of a 250-MW(t), 100-MW(e), pebble bed modular high temperature gas-cooled reactor (HTGR) design with vertical in-line arrangement (i.e., upflow core with steam generators directly above the core). A variety of postulated accident sequences involving combinations of loss of forced primary coolant (helium) circulation, loss of primary coolant pressurization, and loss of heat sink were studied and were discussed

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01; 1 - GPO as TI86002179.

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Additional details

Publishing Information

Imprint Pagination
23 p.
Report number
CONF-851125--15

Conference

Title
American Society of Mechanical Engineers winter annual meeting.
Dates
17-21 Nov 1985.
Place
Miami, FL (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
17028478
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
HEAT SINKS; HTGR TYPE REACTORS; LOSS OF FLOW; LOSSES; PEBBLE BED REACTORS; REACTOR ACCIDENTS; REACTOR SAFETY
Descriptors DEC
ACCIDENTS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HOMOGENEOUS REACTORS; REACTORS; SAFETY; SOLID HOMOGENEOUS REACTORS