Numerical optimisation of the fission-converter and the filter/moderator arrangement for the Boron Neutron Capture Therapy

• Autorzy: Tracz G. , Dąbkowski L. , Dworak D. , Pytel K. , Woźnicka U.
• Języki publikacji: EN

Abstrakty

EN

The paper presents results of the numerical modelling of the fission-converter-based epithermal neutron source designed for a BNCT (Boron Neutron Capture Therapy) facility to be located at the Polish research nuclear reactor MARIA at Świerk. The unique design of the fission converter has been proposed due to a specific geometrical surrounding of the reactor. The filter/moderator arrangement has been optimised in order to moderate fission neutrons to epithermal energies and to get rid of both fast neutrons and photons from the therapeutic beam. The selected filter/moderator set-up ensures both the high epithermal neutron flux and the suitably low level of beam contamination. The elimination of photons originated in the reactor core is an exceptional advantage of the proposed design. It brings one order of magnitude lower gamma radiation dose than the permissible dose in such a type of therapeutic facility is required. The MCNP and FLUKA codes have been used for the computations.

Słowa kluczowe

EN

BNCT; fission converter; Fluka; MCNP; Monte Carlo; neutrons

• Wydawca: Institute of Nuclear Chemistry and Technology
• Czasopismo: Nukleonika
• Rocznik: 2003
• Tom: Vol. 48, nr 4
• Strony: 177--185
• Opis fizyczny: Bibliogr. 7 poz., rys.

Twórcy

autor

Tracz G.

• Department of Environmental and Radiation Transport Physics, The Henryk Niewodniczański Institute of Nuclear Physics, 152 Radzikowskiego Str., 31-342 Kraków, Poland, Tel.: [phone], Fax: [phone]

autor

Dąbkowski L.

• Reactor Analysis and Technology Department, Institute of Atomic Energy, 05-400 Otwock-Świerk, Poland

autor

Dworak D.

• Department of Environmental and Radiation Transport Physics, The Henryk Niewodniczański Institute of Nuclear Physics, 152 Radzikowskiego Str., 31-342 Kraków, Poland, Tel.: [phone], Fax: [phone]

autor

Pytel K.

• Reactor Analysis and Technology Department, Institute of Atomic Energy, 05-400 Otwock-Świerk, Poland

autor

Woźnicka U.

• Department of Environmental and Radiation Transport Physics, The Henryk Niewodniczański Institute of Nuclear Physics, 152 Radzikowskiego Str., 31-342 Kraków, Poland, Tel.: [phone], Fax: [phone]

Bibliografia

• 1. Briesmaister JF (2000) MCNP – a general Monte Carlo n-Particle Transport Code. Version 4C. Report no. LA13709-M. Los Alamos National Laboratory
• 2. Fasso A, Ferrari A, Sala P, Ranft J (1999) FLUKA-99. Milano
• 3. Fluental − http://www.vtt.fi/ket/ket1/bnct/fluental.htm
• 4. Kiger III WS, Sakemoto S, Harling OK (1999) Neutronic design of a fission converter-based epithermal neutron beam for Neutron Capture Therapy. Nucl Sci Eng 131:1−22
• 5. Nigg DW (1999) Some recent trends and progress in the physics and biophysics of Neutron Capture Therapy. Prog Nucl Energy 35;1:79−127
• 6. Pytel K, Dąbkowski J (2001) Optimization of the fission converter for BNCT in MARIA reactor. Assumptions for estimations. IEA report no. B-33/2001. Institute of Atomic Energy, Otwock-Świerk (in Polish)
• 7. Tracz G, Woźnicka U (2002) Optimization of the fission converter and the filter/moderator arrangement for the Boron Neutron Capture Therapy (BNCT). INP report no. 1913/AP. Institute of Nuclear Physics, Kraków (in Polish)
• 8. Woźnicka U, Tracz G, Dworak D (2001) The numerical modeling of the fission-converter-base epithermal neutron source for Boron Neutron Capture Therapy (BNCT). INP report no. 1886/AP. Institute of Nuclear Physics, Kraków (in Polish)