Three groups of CHF test data of non-uniform heating typical grid and guide tube grid were adopted,and the local parameters were obtained by using high precision subchannel code ATHAS.The development of CHF relation suitable for the analysis of fuel assembly deviation from nucleate boiling ratio(DNBR)was completed,and the cold wall effect factor and DNBR limit of guide tube were obtained.Compared with the results of the correlation developed by FLICA,the DNBR limit calculated by the relationship developed by ATHAS is lower,and the prediction rate of axial position of burn-out(BO)point and CHF is higher.
ATHAS codeCritical Heat Flux(CHF)Departure from nucleate boiling ratio(DNBR)
维普
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