Study on the Best Design of Neutron Irradiation Facility for BNCT

  • Otohiko Aizawa
  • Hiroshi Yamada

Abstract

We have two principles for design studies; the first one is the “best design” which has no restrictions in the case of a design of a newly built reactor, and the second one is an “optimum design” which has some restrictions in the case of remodeling for some existing reactors. The first modification of the Musashi reactor was a so-called “optimum design” work1. We have already performed the neutron beam design work2 3 for an enhancement of the thermal and epithermal flux. The present study aims at the “best design” for BNCT, starting from an “optimum design”. The design criteria are as follows: (1) Ф th ≧ 3 × 109(n/cm 2 sec)for thermal beams, (2) Ф epi ≥ 1.5 × 109(n/cm 2 sec) for epithermal beams, on condition of Ф f ≦ 3 × 106 (n/cm 2 sec) and γ ≤ 150(R/h) at the reactor power of 500 KW. If we want to get the flux values for 1 MW reactor, we can easily get them by multiplying the 500 KW values by a factor of 2.

Keywords

Boron 

Preview

Unable to display preview. Download preview PDF.

Unable to display preview. Download preview PDF.

References

  1. 1.
    O. Aizawa, K. Kanda, T. Nozaki and T. Matsumoto, “Remodeling and Dosimetry on the Neutron Irradiation Facility of the Musashi Institute of Technology Research Reactor for Boron Neutron Capture Therapy,” Nucl. Technol., 48; 150 (1980)Google Scholar
  2. 2.
    O. Aizawa, “Research on Neutron Beam Design for BNCT at the Musashi Reactor,” Neutron Beam Design, Development, and Performance for Neutron Capture Therapy, pp. 109–124 (1990)Google Scholar
  3. 3.
    O. Aizawa, “Neutron Beam Design for Enhancement of Thermal and Epithermal Flux at the Musashi Reactor,” Proc. Int. Conference on the Physics of Reactors: Operation, Design and Computation, Vol. 4, pp. 133–142 (1990)Google Scholar
  4. 4.
    W. A. Rhoades and F. R. Mynatt, “The DOT III Two-Dimensional Discrete Ordinate Transport Code,” Oak Ridge National Laboratory, ORNL-TM-4280 (1973)Google Scholar
  5. 5.
    R. W. Roussin, “DCL-75/BUGLE-80 Coupled 47-Neutron, 20-Gamma-ray, P3 Cross-Section Library for LWR Shielding Calculations,” Oak Ridge National Laboratory (1980)Google Scholar

Copyright information

© Springer Science+Business Media New York 1992

Authors and Affiliations

  • Otohiko Aizawa
    • 1
  • Hiroshi Yamada
    • 1
  1. 1.Atomic Energy Research LaboratoryMusashi Institute of TechnologyAsao-ku, KawasakiJapan

Personalised recommendations