Published 1982 | Version v1
Report Restricted

Control rod ejection analysis during a depressurization accident and the development of a rod-ejection-preventing device

Creators

  • 1. Japan Atomic Energy Research Inst., Tokyo

Description

The control rods used for the experimental VHTR are suspended in the core by means of flexible steel cables and it is conceivable that an accidental rod ejection could occur due to a depressurization accident. The computer code AFLADE was developed in order to analyze the possibility of accidental rod ejection, and several studies were performed. The parametric study results showed that the adopted design condition for the VHTR core will not cause a rod ejection accident. In parallel with these accident analyses, a rod-ejection-preventing device was developed in preparation for a hypothetical accident, and its function was verified by the component tests

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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. 148-157.
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
15033338
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPUTER CODES; CONTROL ELEMENTS; CONTROL ROD DRIVES; DEPRESSURIZATION; PRIMARY COOLANT CIRCUITS; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; REACTOR SAFETY; TRANSIENTS; VHTR REACTOR
Descriptors DEC
ACCIDENTS; COOLING SYSTEMS; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; THERMAL REACTORS