G.A.西瓦贝西反应堆低、中活性液体放射性废物源中放射性核素的鉴定与示踪

IF 0.4 4区 工程技术 Q4 NUCLEAR SCIENCE & TECHNOLOGY Kerntechnik Pub Date : 2023-06-29 DOI:10.1515/kern-2022-0113
S. Sriyono, D. Saprudin, M. Rafi, G. R. Sunaryo, Nugraha Luhur, F. A. Muslimu
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引用次数: 0

摘要

摘要G.A.西瓦贝西反应堆(RSG-GAS)产生的放射性液体废物分为低活度放射性液体废物(LALR)和中活度放射性液体废物(MALR)。LALR和MALR的放射性核素含量可以作为反应堆系统、结构和部件(SSC)结构完整性的指标。为了评估反应堆SSC的降解,鉴定了放射性核素种类,并使用伽马能谱测量了它们的活性。根据已识别的放射性核素,可以追踪它们的形成过程。LALR中鉴定出的放射性核素为24Na、51Cr、59Fe、60Co、65Zn和124Sb, MALR中鉴定出的放射性核素为24Na、51Cr、58Co、59Fe、60Co、65Ni、65Zn、89Kr、90Kr、109Cd、131I、132I、140Ba、137Cs、146Ce等。发现的放射性核素可分为腐蚀产物活化(60Co、65Zn、51Cr、59Fe、24Na、65Ni)、黄宝石杂质活化(51Cr、59Fe、60Co、65Zn)、裂变产物(90Kr、140Ba、131I、137Cs等)和脱矿水杂质活化(51Cr、59Fe、65Zn、60Co等)。将各放射性核素的活度值与安全分析报告文件中的极限值进行比较后,可以得出结论,各放射性核素的活度均低于要求水平。由此可以推断,反应堆SSC的结构完整性仍保持良好。在常规监测期间,一次冷却剂中的放射性核素含量随反应堆负荷而波动。当大量或少量的研究样本装载到堆芯上时,检测到的放射性核素浓度会发生变化。然而,他们的活动仍在规定的安全范围内。
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Identification and tracing of radionuclides in low- and medium-activity liquid radwaste sources of G.A. Siwabessy reactor
Abstract The liquid radioactive waste generated by the G.A. Siwabessy reactor (RSG-GAS) is categorized into low-activity liquid radwaste (LALR) and medium-activity liquid radwaste (MALR). The radionuclide content of both LALR and MALR can use as an indicator of the structural integrity of the reactor’s systems, structures, and components (SSC). To evaluate the degradation of the reactor SSC, the radionuclide species were identified, and their activities were measured using gamma spectroscopy. Based on the identified radionuclides, the process of their formation can be traced. The radionuclides identified in LALR were 24Na, 51Cr, 59Fe, 60Co, 65Zn, and 124Sb, while the radionuclides in MALR were 24Na, 51Cr, 58Co, 59Fe, 60Co, 65Ni, 65Zn, 89Kr, 90Kr, 109Cd, 131I, 132I, 140Ba, 137Cs, 146Ce, and several others. The radionuclides found can be classified into corrosion product activation (60Co, 65Zn, 51Cr, 59Fe, 24Na, 65Ni), topaz impurities activation (51Cr, 59Fe, 60Co, 65Zn), fission product (90Kr, 140Ba, 131I, 137Cs, etc.), and demineralized water impurities activation (51Cr, 59Fe, 65Zn, 60Co, etc.). After comparing the activity value of each radionuclide with the limit value in the safety analysis report document, we can conclude that the activity of each one is below the required level. It can infer that the structural integrity of reactor SSC is still well maintain. During routine monitoring, the radionuclide content in the primary coolant fluctuates depending on the reactor load. The concentration of radionuclides detected varies when a large or small number of research samples are loaded onto the core. Nevertheless, their activities remain within the required safety limits.
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来源期刊
Kerntechnik
Kerntechnik 工程技术-核科学技术
CiteScore
0.90
自引率
20.00%
发文量
72
审稿时长
6-12 weeks
期刊介绍: Kerntechnik is an independent journal for nuclear engineering (including design, operation, safety and economics of nuclear power stations, research reactors and simulators), energy systems, radiation (ionizing radiation in industry, medicine and research) and radiological protection (biological effects of ionizing radiation, the system of protection for occupational, medical and public exposures, the assessment of doses, operational protection and safety programs, management of radioactive wastes, decommissioning and regulatory requirements).
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