Obryk Barbara, Malik Klaudia, Bilski Pawel, Igielski Andrzej, Dankowski Jan, Kurowski Arkadiusz, Prokopowicz Rafal, Pytel Krzysztof
Institute of Nuclear Physics Polish Academy of Sciences (IFJ), ul. Radzikowskiego 152, Krakow, Poland.
National Centre for Nuclear Research (NCBJ), ul. A. Soltana 7, Otwock, Poland.
Radiat Prot Dosimetry. 2018 Aug 1;180(1-4):235-239. doi: 10.1093/rpd/ncx244.
Radiation dose was measured with set of TL dosimeters during checkout of neutron radiation hardness of the ORTEC preamplifier type 142A in the experiment at the MARIA nuclear reactor at the National Centre for Nuclear Research (NCBJ), Otwock-Świerk, Poland. Different types of LiF-based TL detectors have been used for measurements in order to evaluate neutron and non-neutron components of the radiation field in the reactor channel during exposure and to check their relevancy for dose measurements in the reactor environment. For high-dose evaluation a new Ultra-High-Temperature Ratio (UHTR) method established for highly sensitive LiF:Mg,Cu,P detectors has been applied. Neutron fluence evaluated from TL measurements was in good agreement with one calculated using neutron flux data during the experiment.
在波兰奥托克-斯维尔克国家核研究中心（NCBJ）的玛丽亚核反应堆进行的实验中，在对ORTEC 142A 型前置放大器进行中子辐射硬度检测期间，使用一组热释光剂量计测量了辐射剂量。为了评估反应堆通道在辐照期间辐射场的中子和非中子成分，并检查它们在反应堆环境中进行剂量测量的相关性，使用了不同类型的基于氟化锂的热释光探测器进行测量。对于高剂量评估，应用了一种为高灵敏度的LiF:Mg,Cu,P探测器建立的新型超高温比（UHTR）方法。通过热释光测量评估的中子注量与实验期间使用中子通量数据计算得到的结果吻合良好。
