Y. Tanimura, H. Yoshitomi, S. Nishino, T. Tsuji, T. Fukami, T. Shinoduka, K. Ohishi, M. Ishii, K. Takamiya, T. Ohnuki, K. Yamasoto, T. Nakanoya, K. Okabe, J. Kamiya
{"title":"从 JAEA 研究堆和加速器设施工作场所的光子光谱测量中评估当前和新的运行数量","authors":"Y. Tanimura, H. Yoshitomi, S. Nishino, T. Tsuji, T. Fukami, T. Shinoduka, K. Ohishi, M. Ishii, K. Takamiya, T. Ohnuki, K. Yamasoto, T. Nakanoya, K. Okabe, J. Kamiya","doi":"10.1016/j.radmeas.2024.107196","DOIUrl":null,"url":null,"abstract":"<div><p>The International Commission on Radiation Units and Measurements (ICRU) has proposed to change the definitions of the operational quantities used for the area and individual monitoring of external exposure in ICRU Report 95. Since introducing new operational quantities into the radiation monitoring may affect the dose assessment using the present personal dosimeters, precise assessments of the influence on monitoring are necessary by characterizing the energy spectrum in the workplace and the energy dependency of the dosimeters to be used. This study measured photon spectra using a NaI(Tl) scintillation detector or a LaBr<sub>3</sub>(Ce) scintillation detector at the Japan Research Reactor No. 3 (JRR-3) and Japan Proton Accelerator Research Complex (J-PARC) workplaces at the Japan Atomic Energy Agency (JAEA). The photon energy spectra were obtained by unfolding the pulse height distributions measured at each workplace. The present and new operational quantities were then evaluated and compared using the spectra measured at the workplaces.</p><p>In JRR-3, the photon energy spectra were measured at the workplaces in the reactor room and thermal neutron beam hall while the reactor was operated. The ambient dose equivalent rates <span><math><mrow><mover><mi>H</mi><mo>˙</mo></mover></mrow></math></span>*(10) at the workplaces were 0.2 μSv·h<sup>−1</sup> – 13 μSv·h<sup>−1</sup>. High energy gamma-rays of 6–7 MeV from <sup>16</sup>N were observed near the fuel failure detection system in the reactor room. Those of 7–8 MeV produced by the thermal neutron capture of iron were observed in the reactor room and the beam hall. In J-PARC, the photon energy spectra were measured at the workplaces in the beam tunnel of the 3 GeV synchrotron beam ring five days after the operation. The ambient dose equivalent rates <span><math><mrow><mover><mi>H</mi><mo>˙</mo></mover></mrow></math></span>*(10) at the workplaces were 35 μSv·h<sup>−1</sup> –430 μSv·h<sup>−1</sup>.</p><p>It was found that the new personal doses, H<sub>p</sub>, were 10%–20% smaller than the present personal dose equivalents, H<sub>p</sub>(10), at the workplaces.</p></div>","PeriodicalId":21055,"journal":{"name":"Radiation Measurements","volume":null,"pages":null},"PeriodicalIF":1.6000,"publicationDate":"2024-06-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Present and new operational quantities evaluated from photon spectrum measurements at workplaces in the research reactor and accelerator facility at the JAEA\",\"authors\":\"Y. Tanimura, H. Yoshitomi, S. Nishino, T. Tsuji, T. Fukami, T. Shinoduka, K. Ohishi, M. Ishii, K. Takamiya, T. Ohnuki, K. Yamasoto, T. Nakanoya, K. Okabe, J. Kamiya\",\"doi\":\"10.1016/j.radmeas.2024.107196\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><p>The International Commission on Radiation Units and Measurements (ICRU) has proposed to change the definitions of the operational quantities used for the area and individual monitoring of external exposure in ICRU Report 95. Since introducing new operational quantities into the radiation monitoring may affect the dose assessment using the present personal dosimeters, precise assessments of the influence on monitoring are necessary by characterizing the energy spectrum in the workplace and the energy dependency of the dosimeters to be used. This study measured photon spectra using a NaI(Tl) scintillation detector or a LaBr<sub>3</sub>(Ce) scintillation detector at the Japan Research Reactor No. 3 (JRR-3) and Japan Proton Accelerator Research Complex (J-PARC) workplaces at the Japan Atomic Energy Agency (JAEA). The photon energy spectra were obtained by unfolding the pulse height distributions measured at each workplace. The present and new operational quantities were then evaluated and compared using the spectra measured at the workplaces.</p><p>In JRR-3, the photon energy spectra were measured at the workplaces in the reactor room and thermal neutron beam hall while the reactor was operated. The ambient dose equivalent rates <span><math><mrow><mover><mi>H</mi><mo>˙</mo></mover></mrow></math></span>*(10) at the workplaces were 0.2 μSv·h<sup>−1</sup> – 13 μSv·h<sup>−1</sup>. High energy gamma-rays of 6–7 MeV from <sup>16</sup>N were observed near the fuel failure detection system in the reactor room. Those of 7–8 MeV produced by the thermal neutron capture of iron were observed in the reactor room and the beam hall. In J-PARC, the photon energy spectra were measured at the workplaces in the beam tunnel of the 3 GeV synchrotron beam ring five days after the operation. 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Present and new operational quantities evaluated from photon spectrum measurements at workplaces in the research reactor and accelerator facility at the JAEA
The International Commission on Radiation Units and Measurements (ICRU) has proposed to change the definitions of the operational quantities used for the area and individual monitoring of external exposure in ICRU Report 95. Since introducing new operational quantities into the radiation monitoring may affect the dose assessment using the present personal dosimeters, precise assessments of the influence on monitoring are necessary by characterizing the energy spectrum in the workplace and the energy dependency of the dosimeters to be used. This study measured photon spectra using a NaI(Tl) scintillation detector or a LaBr3(Ce) scintillation detector at the Japan Research Reactor No. 3 (JRR-3) and Japan Proton Accelerator Research Complex (J-PARC) workplaces at the Japan Atomic Energy Agency (JAEA). The photon energy spectra were obtained by unfolding the pulse height distributions measured at each workplace. The present and new operational quantities were then evaluated and compared using the spectra measured at the workplaces.
In JRR-3, the photon energy spectra were measured at the workplaces in the reactor room and thermal neutron beam hall while the reactor was operated. The ambient dose equivalent rates *(10) at the workplaces were 0.2 μSv·h−1 – 13 μSv·h−1. High energy gamma-rays of 6–7 MeV from 16N were observed near the fuel failure detection system in the reactor room. Those of 7–8 MeV produced by the thermal neutron capture of iron were observed in the reactor room and the beam hall. In J-PARC, the photon energy spectra were measured at the workplaces in the beam tunnel of the 3 GeV synchrotron beam ring five days after the operation. The ambient dose equivalent rates *(10) at the workplaces were 35 μSv·h−1 –430 μSv·h−1.
It was found that the new personal doses, Hp, were 10%–20% smaller than the present personal dose equivalents, Hp(10), at the workplaces.
期刊介绍：
The journal seeks to publish papers that present advances in the following areas: spontaneous and stimulated luminescence (including scintillating materials, thermoluminescence, and optically stimulated luminescence); electron spin resonance of natural and synthetic materials; the physics, design and performance of radiation measurements (including computational modelling such as electronic transport simulations); the novel basic aspects of radiation measurement in medical physics. Studies of energy-transfer phenomena, track physics and microdosimetry are also of interest to the journal.
Applications relevant to the journal, particularly where they present novel detection techniques, novel analytical approaches or novel materials, include: personal dosimetry (including dosimetric quantities, active/electronic and passive monitoring techniques for photon, neutron and charged-particle exposures); environmental dosimetry (including methodological advances and predictive models related to radon, but generally excluding local survey results of radon where the main aim is to establish the radiation risk to populations); cosmic and high-energy radiation measurements (including dosimetry, space radiation effects, and single event upsets); dosimetry-based archaeological and Quaternary dating; dosimetry-based approaches to thermochronometry; accident and retrospective dosimetry (including activation detectors), and dosimetry and measurements related to medical applications.
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