Decontamination of the Activation Product Based on a Legal Revision of the Cyclotron Vault Room on the Non-self-shield Compact Medical Cyclotron
The non-self-shield compact medical cyclotron and the cyclotron vault room were in operation for 27 years. They have now been decommissioned. We efficiently implemented a technique to identify an activation product in the cyclotron vault room. Firstly, the distribution of radioactive concentrations...
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Veröffentlicht in: | Japanese Journal of Radiological Technology 2016, Vol.72(10), pp.989-998 |
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creator | Komiya, Isao Umezu, Yoshiyuki Fujibuchi, Toshioh Nakamura, Kazumasa Baba, Shingo Honda, Hiroshi |
description | The non-self-shield compact medical cyclotron and the cyclotron vault room were in operation for 27 years. They have now been decommissioned. We efficiently implemented a technique to identify an activation product in the cyclotron vault room. Firstly, the distribution of radioactive concentrations in the concrete of the cyclotron vault room was estimated by calculation from the record of the cyclotron operation. Secondly, the comparison of calculated results with an actual measurement was performed using a NaI scintillation survey meter and a high-purity germanium detector. The calculated values were overestimated as compared to the values measured using the NaI scintillation survey meter and the high-purity germanium detector. However, it could limit the decontamination area. By simulating the activation range, we were able to minimize the concrete core sampling. Finally, the appropriate range of radioactivated area in the cyclotron vault room was decontaminated based on the results of the calculation. After decontamination, the radioactive concentration was below the detection limit value in all areas inside the cyclotron vault room. By these procedures, the decommissioning process of the cyclotron vault room was more efficiently performed. |
doi_str_mv | 10.6009/jjrt.2016_JSRT_72.10.989 |
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They have now been decommissioned. We efficiently implemented a technique to identify an activation product in the cyclotron vault room. Firstly, the distribution of radioactive concentrations in the concrete of the cyclotron vault room was estimated by calculation from the record of the cyclotron operation. Secondly, the comparison of calculated results with an actual measurement was performed using a NaI scintillation survey meter and a high-purity germanium detector. The calculated values were overestimated as compared to the values measured using the NaI scintillation survey meter and the high-purity germanium detector. However, it could limit the decontamination area. By simulating the activation range, we were able to minimize the concrete core sampling. Finally, the appropriate range of radioactivated area in the cyclotron vault room was decontaminated based on the results of the calculation. After decontamination, the radioactive concentration was below the detection limit value in all areas inside the cyclotron vault room. By these procedures, the decommissioning process of the cyclotron vault room was more efficiently performed.</description><identifier>ISSN: 0369-4305</identifier><identifier>EISSN: 1881-4883</identifier><identifier>DOI: 10.6009/jjrt.2016_JSRT_72.10.989</identifier><identifier>PMID: 27760910</identifier><language>eng ; jpn</language><publisher>Japan: Japanese Society of Radiological Technology</publisher><subject>Activation ; compact medical cyclotron ; Cyclotrons ; Decontamination ; Decontamination - instrumentation ; Detectors ; Mathematical analysis ; Measuring instruments ; non-self-shield ; Radiation Protection - instrumentation ; radioactive concentration ; radioactive waste ; Radioactivity ; Technology, Radiologic - instrumentation ; Vaults</subject><ispartof>Japanese Journal of Radiological Technology, 2016, Vol.72(10), pp.989-998</ispartof><rights>2016 Japanese Society of Radiological Technology</rights><oa>free_for_read</oa><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c4189-d5a5d02cabda59719093b7909ed359cbb880e20d907da061f8c568c82ed4d2f83</citedby><cites>FETCH-LOGICAL-c4189-d5a5d02cabda59719093b7909ed359cbb880e20d907da061f8c568c82ed4d2f83</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><link.rule.ids>314,780,784,27924,27925</link.rule.ids><backlink>$$Uhttps://www.ncbi.nlm.nih.gov/pubmed/27760910$$D View this record in MEDLINE/PubMed$$Hfree_for_read</backlink></links><search><creatorcontrib>Komiya, Isao</creatorcontrib><creatorcontrib>Umezu, Yoshiyuki</creatorcontrib><creatorcontrib>Fujibuchi, Toshioh</creatorcontrib><creatorcontrib>Nakamura, Kazumasa</creatorcontrib><creatorcontrib>Baba, Shingo</creatorcontrib><creatorcontrib>Honda, Hiroshi</creatorcontrib><title>Decontamination of the Activation Product Based on a Legal Revision of the Cyclotron Vault Room on the Non-self-shield Compact Medical Cyclotron</title><title>Japanese Journal of Radiological Technology</title><addtitle>Jpn. J. Radiol. Technol.</addtitle><description>The non-self-shield compact medical cyclotron and the cyclotron vault room were in operation for 27 years. They have now been decommissioned. We efficiently implemented a technique to identify an activation product in the cyclotron vault room. Firstly, the distribution of radioactive concentrations in the concrete of the cyclotron vault room was estimated by calculation from the record of the cyclotron operation. Secondly, the comparison of calculated results with an actual measurement was performed using a NaI scintillation survey meter and a high-purity germanium detector. The calculated values were overestimated as compared to the values measured using the NaI scintillation survey meter and the high-purity germanium detector. However, it could limit the decontamination area. By simulating the activation range, we were able to minimize the concrete core sampling. Finally, the appropriate range of radioactivated area in the cyclotron vault room was decontaminated based on the results of the calculation. After decontamination, the radioactive concentration was below the detection limit value in all areas inside the cyclotron vault room. By these procedures, the decommissioning process of the cyclotron vault room was more efficiently performed.</description><subject>Activation</subject><subject>compact medical cyclotron</subject><subject>Cyclotrons</subject><subject>Decontamination</subject><subject>Decontamination - instrumentation</subject><subject>Detectors</subject><subject>Mathematical analysis</subject><subject>Measuring instruments</subject><subject>non-self-shield</subject><subject>Radiation Protection - instrumentation</subject><subject>radioactive concentration</subject><subject>radioactive waste</subject><subject>Radioactivity</subject><subject>Technology, Radiologic - instrumentation</subject><subject>Vaults</subject><issn>0369-4305</issn><issn>1881-4883</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2016</creationdate><recordtype>article</recordtype><sourceid>EIF</sourceid><recordid>eNqNkc1u1DAUhS0EoqPSV0BesslgJ3ZiL8tA-dFA0VDYWo590_EoiQfbqdS34JFxlDLqgkU319K53zlX1kEIU7KuCZFvD4eQ1iWhtfryY3ejmnKdN1LIZ2hFhaAFE6J6jlakqmXBKsLP0EWMriXZmyXCXqKzsmlqIilZoT_vwfgx6cGNOjk_Yt_htAd8aZK7W5TvwdvJJPxOR7A4Cxpv4Vb3eAd3Lj7ybO5N71PIwi899QnvvB9mft5982MRoe-KuHfQW7zxw1Hn0K9gnclZJ-8r9KLTfYSLh_cc_bz6cLP5VGyvP37eXG4Lw6iQheWaW1Ia3VrNZUNl_lzb5Am24tK0rRAESmIlaawmNe2E4bUwogTLbNmJ6hy9WXKPwf-eICY1uGig7_UIfoqKippxzjihT0A5aQRjdfkEtOKcME7rjIoFNcHHGKBTx-AGHe4VJWouWs1Fq8dFz5tcdLa-frgytQPYk_FfrRm4XoBDTPoWToAOyZkeluQlL8__nDiRZq-DgrH6CylQwpw</recordid><startdate>20160101</startdate><enddate>20160101</enddate><creator>Komiya, Isao</creator><creator>Umezu, Yoshiyuki</creator><creator>Fujibuchi, Toshioh</creator><creator>Nakamura, Kazumasa</creator><creator>Baba, Shingo</creator><creator>Honda, Hiroshi</creator><general>Japanese Society of Radiological Technology</general><scope>CGR</scope><scope>CUY</scope><scope>CVF</scope><scope>ECM</scope><scope>EIF</scope><scope>NPM</scope><scope>AAYXX</scope><scope>CITATION</scope><scope>7X8</scope><scope>7QO</scope><scope>8FD</scope><scope>FR3</scope><scope>P64</scope><scope>7SC</scope><scope>7U5</scope><scope>JQ2</scope><scope>L7M</scope><scope>L~C</scope><scope>L~D</scope></search><sort><creationdate>20160101</creationdate><title>Decontamination of the Activation Product Based on a Legal Revision of the Cyclotron Vault Room on the Non-self-shield Compact Medical Cyclotron</title><author>Komiya, Isao ; Umezu, Yoshiyuki ; Fujibuchi, Toshioh ; Nakamura, Kazumasa ; Baba, Shingo ; Honda, Hiroshi</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c4189-d5a5d02cabda59719093b7909ed359cbb880e20d907da061f8c568c82ed4d2f83</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng ; jpn</language><creationdate>2016</creationdate><topic>Activation</topic><topic>compact medical cyclotron</topic><topic>Cyclotrons</topic><topic>Decontamination</topic><topic>Decontamination - instrumentation</topic><topic>Detectors</topic><topic>Mathematical analysis</topic><topic>Measuring instruments</topic><topic>non-self-shield</topic><topic>Radiation Protection - instrumentation</topic><topic>radioactive concentration</topic><topic>radioactive waste</topic><topic>Radioactivity</topic><topic>Technology, Radiologic - instrumentation</topic><topic>Vaults</topic><toplevel>online_resources</toplevel><creatorcontrib>Komiya, Isao</creatorcontrib><creatorcontrib>Umezu, Yoshiyuki</creatorcontrib><creatorcontrib>Fujibuchi, Toshioh</creatorcontrib><creatorcontrib>Nakamura, Kazumasa</creatorcontrib><creatorcontrib>Baba, Shingo</creatorcontrib><creatorcontrib>Honda, Hiroshi</creatorcontrib><collection>Medline</collection><collection>MEDLINE</collection><collection>MEDLINE (Ovid)</collection><collection>MEDLINE</collection><collection>MEDLINE</collection><collection>PubMed</collection><collection>CrossRef</collection><collection>MEDLINE - Academic</collection><collection>Biotechnology Research Abstracts</collection><collection>Technology Research Database</collection><collection>Engineering Research Database</collection><collection>Biotechnology and BioEngineering Abstracts</collection><collection>Computer and Information Systems Abstracts</collection><collection>Solid State and Superconductivity Abstracts</collection><collection>ProQuest Computer Science Collection</collection><collection>Advanced Technologies Database with Aerospace</collection><collection>Computer and Information Systems Abstracts Academic</collection><collection>Computer and Information Systems Abstracts Professional</collection><jtitle>Japanese Journal of Radiological Technology</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Komiya, Isao</au><au>Umezu, Yoshiyuki</au><au>Fujibuchi, Toshioh</au><au>Nakamura, Kazumasa</au><au>Baba, Shingo</au><au>Honda, Hiroshi</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Decontamination of the Activation Product Based on a Legal Revision of the Cyclotron Vault Room on the Non-self-shield Compact Medical Cyclotron</atitle><jtitle>Japanese Journal of Radiological Technology</jtitle><addtitle>Jpn. J. Radiol. Technol.</addtitle><date>2016-01-01</date><risdate>2016</risdate><volume>72</volume><issue>10</issue><spage>989</spage><epage>998</epage><pages>989-998</pages><issn>0369-4305</issn><eissn>1881-4883</eissn><abstract>The non-self-shield compact medical cyclotron and the cyclotron vault room were in operation for 27 years. They have now been decommissioned. We efficiently implemented a technique to identify an activation product in the cyclotron vault room. Firstly, the distribution of radioactive concentrations in the concrete of the cyclotron vault room was estimated by calculation from the record of the cyclotron operation. Secondly, the comparison of calculated results with an actual measurement was performed using a NaI scintillation survey meter and a high-purity germanium detector. The calculated values were overestimated as compared to the values measured using the NaI scintillation survey meter and the high-purity germanium detector. However, it could limit the decontamination area. By simulating the activation range, we were able to minimize the concrete core sampling. Finally, the appropriate range of radioactivated area in the cyclotron vault room was decontaminated based on the results of the calculation. After decontamination, the radioactive concentration was below the detection limit value in all areas inside the cyclotron vault room. By these procedures, the decommissioning process of the cyclotron vault room was more efficiently performed.</abstract><cop>Japan</cop><pub>Japanese Society of Radiological Technology</pub><pmid>27760910</pmid><doi>10.6009/jjrt.2016_JSRT_72.10.989</doi><tpages>10</tpages><oa>free_for_read</oa></addata></record> |
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subjects | Activation compact medical cyclotron Cyclotrons Decontamination Decontamination - instrumentation Detectors Mathematical analysis Measuring instruments non-self-shield Radiation Protection - instrumentation radioactive concentration radioactive waste Radioactivity Technology, Radiologic - instrumentation Vaults |
title | Decontamination of the Activation Product Based on a Legal Revision of the Cyclotron Vault Room on the Non-self-shield Compact Medical Cyclotron |
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