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Monte-Carlo calculations for the development of a BNCT neutron source at the Kyiv Research Reactor
O O Gritzay1, O I Kalchenko, N A Klimova
1Institute for Nuclear Research, Kyiv, Ukraine. ogritzay@kinr.kiev.ua
Abstract:
The results presented in this paper display our continuing steps toward development of a neutron source with parameters required by boron neutron capture therapy (BNCT) at the Kyiv Research Reactor (KRR). The purpose of this work was: 1. calculation of the neutron flux which can be achieved at the greatest possible approach of a patient to the reactor core; 2. analysis of the influence of a nickel collimator and a nickel-60 filter on the characteristics of the neutron beam; 3. creation and validation of the MCNP calculational pattern for an actual core fuel load in the KRR. Results of calculations were carried out by means of the MCNP4C code included: 1. An epithermal neutron flux of 3x10(9)-5x10(9)neutron/cm(2)s with an epithermal-to-fast flux ratio of 80-230 could be obtained at the KRR, using a natural nickel layer on the interior borated polyethylene collimator wall and a (60)Ni filter. 2. Use of the (60)Ni filter may be useful to increase the ratio epithermal-to-fast flux without a substantial decrease in the magnitude of the epithermal neutron flux. 3. The MCNP model proposed in this paper could also be useful for reactor safety calculations.
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