Analysis of air ingress process during the primary-pipe rupture accident of the HTGR
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Description
In order to predict or analyze the process of air ingress during the primary-pipe rupture accident of HTGRs, it is very important to develop computer programs and to validate them by experiments. This paper describes a computer program, which is named FLOWGR, developed to analyze the process of air ingress during the first stage of the primary-pipe rupture accident. FLOWGR provides a numerical method for analyzing the transient thermal hydraulic behavior by solving the one-dimensional basic equations for continuity, momentum conservation, energy conservation of the gas mixture, and mass conservation of each gas species. The numerical results are in good agreement with the experimental ones regarding the density of the gas mixture, the concentration of each gas species produced by the graphite oxidation reaction and the onset time of the natural circulation of air. (author)
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Additional details
Publishing Information
- Imprint Title
- Proceedings of the 3rd JAERI symposium on HTGR technologies
- Imprint Pagination
- 546 p.
- Journal Page Range
- p. 272-288.
- Report number
- JAERI-Conf--96-010
Conference
- Title
- 3. JAERI symposium on HTGR technologies.
- Dates
- 15-16 Feb 1996.
- Place
- Oarai, Ibaraki (Japan).
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 28026067
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AIR; CONTINUITY EQUATIONS; F CODES; GASES; GRAPHITE; HTGR TYPE REACTORS; LOSS OF COOLANT; MIXTURES; NUMERICAL SOLUTION; OXIDATION; PRIMARY COOLANT CIRCUITS; REACTOR CORES; RUPTURES; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; CARBON; CHEMICAL REACTIONS; COMPUTER CODES; COOLING SYSTEMS; DIFFERENTIAL EQUATIONS; DISPERSIONS; ELEMENTS; EQUATIONS; FAILURES; FLUIDS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; NONMETALS; PARTIAL DIFFERENTIAL EQUATIONS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS