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Tsiklauri, G.V.; Schmitt, B.E.
Pacific Northwest Lab., Richland, WA (United States). Funding organisation: USDOE, Washington, DC (United States)1995
Pacific Northwest Lab., Richland, WA (United States). Funding organisation: USDOE, Washington, DC (United States)1995
AbstractAbstract
[en] The capability of the RELAP5/MOD3 code to validate various transients encountered in RBMK reactor postulated accidents has been assessed. The assessment results include a loss of coolant accident at the inlet of the core pressure tube, the blockage of a pressure tube, and the pressure response of the core cavity to in core pressure tube ruptures. These assessments show that the RELAP5/MOD3 code can predict major phenomena during postulated accidents in the RBMK reactors
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Jun 1995; 40 p; CONTRACT AC06-76RL01830; Also available from OSTI as DE95013853; NTIS; US Govt. Printing Office Dep
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