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热释光剂量仪和固态核径迹探测器在燃料制造设施中的运行比较

Operational comparison of TLD albedo dosemeters and solid state nuclear tracks detectors in fuel fabrication facilities.

作者信息

Tsujimura N, Takada C, Yoshida T, Momose T

机构信息

Radiation Protection Division, Japan Nuclear Cycle Development Institute, 4-33, Tokai, Ibaraki 319-1194, Japan.

出版信息

Radiat Prot Dosimetry. 2007;125(1-4):383-6. doi: 10.1093/rpd/ncm159. Epub 2007 Mar 3.

Abstract

The authors carried out an operational study that compared the use of TLD albedo dosemeters and solid state nuclear tracks detector in plutonium environments of Japan Nuclear Cycle Development Institute, Tokai Works. A selected group of workers engaged in the fabrication process of MOX (Plutonium-Uranium mixed oxide) fuel wore both TLD albedo dosemeters and solid state nuclear tracks detectors. The TL readings were generally proportional to the counted etch-pits, and thus the dose equivalent results obtained from TLD albedo dosemeter agreed with those from solid state nuclear tracks detector within a factor of 1.5. This result indicates that, in the workplaces of the MOX fuel plants, the neutron spectrum remained almost constant in terms of time and space, and the appropriate range of field-specific correction with spectrum variations was small in albedo dosimetry.

摘要

作者开展了一项运行研究,比较了热释光反照率剂量计和固态核径迹探测器在日本核循环开发机构东海事业所钚环境中的使用情况。一组从事混合氧化物(钚 - 铀混合氧化物)燃料制造过程的选定工人同时佩戴了热释光反照率剂量计和固态核径迹探测器。热释光读数通常与蚀刻坑计数成正比,因此热释光反照率剂量计获得的剂量当量结果与固态核径迹探测器获得的结果在1.5倍的范围内一致。该结果表明,在混合氧化物燃料厂的工作场所,中子能谱在时间和空间方面几乎保持恒定,并且在反照率剂量测定中,随能谱变化的特定场修正的适当范围较小。

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