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首页> 外文期刊>IEEE Transactions on Nuclear Science >Assessment of on-line burnup monitoring of pebble bed reactor fuel using passive gamma-ray spectrometry
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Assessment of on-line burnup monitoring of pebble bed reactor fuel using passive gamma-ray spectrometry

机译:使用无源伽马射线光谱法评估卵石床反应堆燃料的在线燃尽监测

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An investigation was performed to assess the feasibility of passive gamma-ray spectrometry assay as an approach for on-line burnup determination for the Modular Pebble Bed Reactor (MPBR). In addition to its inherently safe design, a unique feature of this reactor is its multipass fuel cycle in which graphite fuel pebbles are randomly loaded and continuously circulated through the core until they reach their prescribed end-of-life burnup limit (/spl sim/80 000 MWD/MTU). Unlike the situation with conventional light water reactors, depending solely on computational methods to perform in-core fuel management will be highly inaccurate. As a result, an on-line measurement approach becomes the only accurate method to assess whether a particular pebble has reached its end-of-life burnup limit. The results of this investigation indicate that the fission products Cs-137 and Eu-154 have the potential to provide accurate and power-history-resistant signatures that can be directly correlated with burnup. Furthermore, depending on the fuel manufacturing process, artificially introduced dopants (e.g., Co) can provide gamma-ray lines that are usable for burnup monitoring. In fact, it was found that the relative activity of Co-60 to Cs-134 could form a burnup indicator that is resistant to power-history variations. In this case, the use of a relative indicator has several advantages, among them the elimination of the need for absolute knowledge of the detector full-energy peak efficiency curve and the establishment of a system quality-assurance figure of merit based on the peak area ratio of the Co lines.
机译:进行了一项研究,以评估被动式伽马射线光谱分析法作为模块化卵石床反应器(MPBR)在线燃耗测定方法的可行性。除了其固有的安全设计外,该反应堆的独特之处还在于其多程燃料循环,其中,石墨燃料小卵石被随机加载并不断在堆芯中循环,直到达到规定的使用寿命极限(/ spl sim / 80 000 MWD / MTU)。与常规轻水反应堆的情况不同,仅依靠计算方法来执行堆芯内燃料管理将非常不准确。结果,在线测量方法成为评估特定卵石是否已达到其使用寿命极限的唯一准确方法。这项研究的结果表明,裂变产物Cs-137和Eu-154具有提供准确和耐功率历史特征的潜力,可直接与燃耗相关。此外,取决于燃料的制造过程,人工引入的掺杂剂(例如,Co)可以提供可用于燃尽监测的伽马射线线。实际上,已经发现Co-60与Cs-134的相对活性可以形成对功率历史变化有抵抗力的燃尽指标。在这种情况下,使用相对指示符具有多个优点,其中包括无需绝对了解检测器的全能量峰值效率曲线,并且无需根据峰值面积建立系统质量保证指标Co线的比率。

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