Monte-Carlo calculations for the development of a BNCT neutron source at the Kyiv Research Reactor.
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.
Gritzay
O O
OO
Institute for Nuclear Research, Kyiv, Ukraine. ogritzay@kinr.kiev.ua
Kalchenko
O I
OI
Klimova
N A
NA
Razbudey
V F
VF
Sanzhur
A I
AI
Binney
S E
SE
D016754:Boron Neutron Capture Therapy / Q000295:instrumentation* / Q000706:statistics & numerical data*; D004867:Equipment Design; D005214:Fast Neutrons / Q000627:therapeutic use; D005374:Filtration / Q000295:instrumentation; D006801:Humans; D007554:Isotopes; D009010:Monte Carlo Method; D009532:Nickel; D011880:Radiotherapy Planning, Computer-Assisted / Q000706:statistics & numerical data; D014455:Ukraine
D007554:Isotopes; D009532:Nickel