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The Calculation accuracy analysis of the core design code for ATR (Advanced Thermal Reactor) demonstration plant; Control rod reactivity worth and DCA power distribution

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The calculation accuracy evaluation of the control rods reactivity worths and channel power distributions were performed on the basis of DCA experimental data and "Fugen" start-up test data by using the WIMS-ATR code. The main results which have been obtained are as follows. (1)It is proved that calculation values by the WIMS-ATR code over-estimates the B$$_{4}$$C control rods worths about 4%-9% compared with the METHUSELAH-II code. (2)The calculation accuracy of the B$$_{4}$$C control rods worths based on the "new" absorption area method used cell averaged diffusion constants by the WIMS-ATR code is about -6% $$sim$$ +8%. From this result, it is proposed to use $$pm$$10% as the design margin to the control rod reactivity worths. (3)It is considered that the multi-cell method using imhomogenious nuclear constants by using the WIMS-ATR code is able to estimate the control rods reactivity worths with the errors of about $$pm$$5%. Therefore, it is proposed to use the multi-cell analysis method as a detailed calculational method for reevaluation of design values for control rods reactivity worths. (4)The RMS (Root Mean Square) of the calculation errors of the cannel power distributions is about 2 $$sim$$ 3%. Therefore, it is shown that the calculational values by the WIMS-ATR code are in good agreement with the experimental data.

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