Published 1982 | Version v1
Report Restricted

Safety and licensing analyses for the Fort St. Vrain HTGR

Creators

  • 1. Oak Ridge National Lab., TN

Description

The Oak Ridge National Laboratory (ORNL) safety analysis program for the HTGR includes development and verification of system response simulation codes, and applications of these codes to specific Fort St. Vrain reactor licensing problems. Licensing studies addressed the oscillation problems and the concerns about large thermal stresses in the core support blocks during a postulated accident

Files

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Additional details

Publishing Information

Imprint Title
Third Japan-US seminar on HTGR safety technology: proceedings. Volume I
Journal Page Range
p. 215-230.
Report number
NUREG/CP--0045-Vol.1

Conference

Title
3. Japan/US HTGR safety technology seminar.
Dates
2-3 Jun 1982.
Place
Upton, NY (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
15033340
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPUTER CODES; COMPUTERIZED SIMULATION; CONTROL ELEMENTS; HEAT TRANSFER; HYDRAULICS; LICENSING; REACTIVITY INSERTIONS; REACTOR ACCIDENTS; REACTOR CORE RESTRAINTS; REACTOR CORES; REACTOR SAFETY; STEAM GENERATORS; SYSTEMS ANALYSIS; THERMAL STRESSES; TRANSIENTS; VRAIN REACTOR
Descriptors DEC
ACCIDENTS; BOILERS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HTGR TYPE REACTORS; POWER REACTORS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; REACTORS; RESTRAINTS; SAFETY; SIMULATION; STRESSES; VAPOR GENERATORS