Published March 2000 | Version v1
Book

Protection quantities and conversion coefficients for use in radiation shielding

  • 1. INFN, Laboratori Nazionali di Frascati, Frascati (Italy)

Description

Two types of quantities are specifically defined for use in radiological protection: protection quantities and operational quantities. In order to determine these quantities, conversion coefficients from physical quantities are needed. The International bodies provided such coefficients for photons and electrons of energy up to 10 MeV and for neutrons of energy up to 180 MeV. For purposes of shielding calculation around high-energy accelerators, conversion coefficients for other types of radiation and higher energies need to be calculated. Coefficients appropriate for radiation shielding estimates, calculated by the Monte Carlo transport code FLUKA, are summarised and discussed in this paper. Some significant examples of applications of the calculated conversion coefficients for accelerator shielding purposes are presented. On the basis of preliminary results, the effective dose for PA (Ante ro-Posterior Geometry) incidence seems to be the most appropriate quantify for a conservative estimate of the shields. (author)

Availability note (English)

Available from the Internet at URL https://doi.org/10.1080/00223131.2000.10875010
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. 850-854

Conference

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

Optional Information

Notes
26 refs., 6 figs., 1 tab.; This record replaces 31061546 Imprint:Published in Journal of Nuclear Science and Technology, Suppl. 1