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.
Institute for Nuclear Research, Kyiv, Ukraine. ogritzay@kinr.kiev.ua
O O
OO
Gritzay
O I
OI
Kalchenko
N A
NA
Klimova
V F
VF
Razbudey
A I
AI
Sanzhur
S E
SE
Binney
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