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首页> 外文会议>International Conference on Advances in Destructive and Non-Destructive Analysis for Environmental Monitoring and Nuclear Forensics; 20021021-20021023; Karlsruhe; DE >RADIOCHEMICAL ASSESSMENT OF CORE WATER AS AN INDICATOR OF FUEL RELIABILITY BEHAVIOUR: A CASE STUDY
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RADIOCHEMICAL ASSESSMENT OF CORE WATER AS AN INDICATOR OF FUEL RELIABILITY BEHAVIOUR: A CASE STUDY

机译：核燃料作为燃料可靠性行为指标的放射化学评估：案例研究

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Evaluation of coolant activity during nuclear reactor operation is the first step in assessing fuel reliability. Monitoring the activity of selected fission product isotopes in the off-gas system or in the primary coolant provides useful information on fuel status. Non-destructive and destructive methods were used to determine fission products as well as activation products in liquid samples taken from the ET-RR-1 research reactor core water, and examined for indications of fuel leakage during operation. The ET-RR1 is a 2 MW light water reactor at Inshass, Egypt, operated with aluminium cladded 10% enriched uranium oxide. Gamma spectrometry, based on a hyperpure germanium detector, was used to evaluate specific activities of present radionuclides. The release rate of ~(137)Cs was used to characterize the fuel assemblies while investigating the presence of corrosion pits along the external fuel clad. Radiochemical analysis of core water before and 1 h after full power operation indicated high activity of ~(137)Cs. About 70% of the ~(137)Cs was already present in the core water before operation. Caesium-137 to ~(60)Co ratios, before and after operation, were similar at 274 and 210, respectively. As ~(239)Np was detected in core water after operation (58 ± 1.4 kBq·L~(-1)), the total uranium content in the water before operation was determined using laser fluorimetry to evaluate U traceability, if any. The total uranium content of the core water before and after operation was 0.9 and 1.6 ppm, while water samples from the new and old spent fuel pools showed 1.2 and 2.1 ppm, respectively. Neptunium-239 can be effectively employed as an indicator of degraded fuel conditions and of significant fuel loss. Among others, ~(131)I, ~(133)I, ~(135)Xe, ~(134)Cs, ~(l37)Cs, ~(91)Sr, ~(90)Sr, ~(140)La and ~(140)Ba were determined. The specific activities of ~(137)Cs and ~(90)Sr measured in the reactor core water before and after operation were about 18 and 12.7 kBq·L~(-1), and 26 and 15.3 kBq·L~(-1), respectively. The specific activities of ~(134)Cs, ~(137)Cs, and ~(90)Sr in water samples from the new spent-fuel pool were 753,43, and 41 kBq L~(-1), respectively, in comparison with 3.4,128 and 113 kBq·L~(-1) in water samples from the old spent fuel pool. These findings raise questions about possible fuel failure and the efficiency of the purification system for water treatment.
机译：核反应堆运行期间对冷却剂活性的评估是评估燃料可靠性的第一步。监测废气系统或一次冷却剂中选定裂变产物同位素的活动可提供有关燃料状态的有用信息。非破坏性和破坏性方法用于确定从ET-RR-1研究堆堆芯水中获取的液体样品中的裂变产物和活化产物，并检查了运行期间燃料泄漏的迹象。 ET-RR1是埃及Inshass的2 MW轻水反应堆，使用铝包覆的10％浓缩铀氧化物进行操作。基于超纯锗探测器的伽马能谱法用于评估当前放射性核素的比活度。 〜（137）Cs的释放速率用于表征燃料组件，同时研究沿外部燃料包层的腐蚀坑的存在。全功率运行之前和之后1 h的核心水的放射化学分析表明〜（137）Cs具有较高的活性。作业前，核心水中已经存在约70％的〜（137）Cs。手术前和手术后Ca-137与〜（60）Co的比率分别相似，分别为274和210。由于操作后在核心水中检测到〜（239）Np（58±1.4 kBq·L〜（-1）），因此使用激光荧光法确定操作前水中的总铀含量，以评估U的可追溯性（如果有）。作业前后核心水中的铀总含量分别为0.9和1.6 ppm，而新旧废燃料池的水样分别显示为1.2和2.1 ppm。 Neptunium-239可以有效地用作降低燃料状况和显着燃料损失的指标。其中，〜（131）I，〜（133）I，〜（135）Xe，〜（134）Cs，〜（137）Cs，〜（91）Sr，〜（90）Sr，〜（140）La确定〜（140）Ba。操作前后反应堆堆芯水中测得的〜（137）Cs和〜（90）Sr的比活分别为18和12.7 kBq·L〜（-1），26和15.3 kBq·L〜（-1） ）， 分别。在新的乏燃料池中，水样中〜（134）Cs，〜（137）Cs和〜（90）Sr的比活分别为753,43和41 kBq L〜（-1）。与旧乏燃料池水样中的3.4,128和113 kBq·L〜（-1）进行比较。这些发现提出了有关可能的燃料故障和水处理净化系统效率的问题。

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