Published March 2000 | Version v1
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Evaluation of the shielding design of the primary cooling system in the prototype FBR Monju

  • 1. Hitachi Engineering Co. Ltd., Ibaraki (Japan)
  • 2. Japan Nuclear Cycle Development Institute, Tsuruga, Fukui (Japan)
  • 3. Japan Atomic Power Co., Tokyo (Japan)
  • 4. Nuclear Energy System Incorporated, Tsuruga, Fukui (Japan)

Description

As part of the start-up tests of the prototype fast breeder reactor Monju, the activities of 24Na and 22Na, which are generated by neutron irradiation of the primary sodium, were measured. The gamma-ray dose rates resulting from these nuclides inside the primary heat transport system cell were also measured. This paper presents an outline of the measurement methods and results, the design requirements and the design margins, which were evaluated by comparing the measurements with the calculations based on FBR shielding analysis methods. (author)

Availability note (English)

Available from the Internet at URL https://doi.org/10.1080/00223131.2000.10874853
Part of:
Proceedings of ninth international conference on radiation shielding

Additional details

Publishing Information

Publisher
Atomic Energy Society of Japan
Imprint Place
Tokyo (Japan)
Imprint Title
Proceedings of ninth international conference on radiation shielding
Imprint Pagination
906 p.
Journal Page Range
p. 94-98

Conference

Title
9. international conference on radiation shielding
Acronym
ICRS-9
Dates
17-22 Oct 1999
Place
Tsukuba, Ibaraki (Japan)

Optional Information

Notes
7 refs., 11 figs., 2 tabs.; This record replaces 31057867 Imprint:Published in Journal of Nuclear Science and Technology, Suppl. 1