Activation evaluation of substances around the target in 70-MeV proton beam irradiation facilities
- 주제(키워드) 70-MeV proton beam · Activation · FISPACT-II · Measurement · Clearance level
- 발행기관 한국물리학회
- 발행년도 2023
- 총서유형 Journal
- DOI http://dx.doi.org/10.1007/s40042-023-00803-z
- KCI ID ART002966356
- 본문언어 영어
초록/요약
Various substances in the target room of 70-MeV proton beam irradiation facility must be managed as radioactive waste owing to their activation during operations. In radioactive waste management, it is important to calculate the storage period. Consequently, radionuclides of activated substances and radioactivity concentration must be investigated. This study investi gated the radionuclides and radioactivity values of activated aluminum, concrete, stainless steel, and each concrete by depth using computational simulations (Monte Carlo N-Particle, FISPACT-II) and measurements. Most of the radionuclides and radioactivity values of the substances obtained by the two methods exceeded the clearance level. For nuclides exceeding the clearance level, the ratio of the FISPACT-II to measurement results yielded an average of 1.21. With increase in the depth of the concrete, the diference between the two results increased. For all substances, the period of satisfying the clearance criterion was more than 10 years. This long period is attributed to the efects of long half-life nuclides 22Na and 54Mn. Thus, when calculating the storage period for radioactive waste disposal, the method resulting in higher activity values for 22Na and 54Mn should be applied.
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