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Radiation Protection Dosimetry Advance Access originally published online on December 12, 2006
Radiation Protection Dosimetry 2007 123(4):417-425; doi:10.1093/rpd/ncl475
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© The Author 2006. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oxfordjournals.org

Evaluation of the radioactivity of the pre-dominant gamma emitters in components used at high-energy proton accelerator facilities

M. Numajiri*

Radiation Science Center, High Energy Accelerator Research Organization (KEK), Tsukuba, Ibaraki 305-0801, Japan

* Corresponding author: masaharu.numajiri{at}kek.jp

Received June 20, 2006, amended October 14, 2006, accepted October 28, 2006


  Abstract

At a high-energy, high-intensity proton accelerator facility, the accelerator components inside the beam-line tunnel and the concrete wall of the tunnel are activated due to beam loss during operation. During maintenance work inside the tunnel, radiation emitted from these activated materials can cause exposure to radiation workers. In this study, the relation between the surface dose rate of activated materials and the induced radioactivity was considered, and an evaluation of the major radioactivity using the surface dose rate was made. It has been revealed that 22Na in Al samples and 54Mn in Fe samples, 60Co and 54Mn in Fe samples, and 60Co in Fe and Cu samples are principal residual radionuclides after a few hundred days of cooling about a few years of cooling and ~10 y of cooling, respectively.


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