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RADSOURCE: A COMPUTER PROGRAM FOR PREDICTING SCALING FACTORS

机译:Radsource:用于预测缩放因子的计算机程序

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RADSOURCE is a microcomputer program that analyzes reactor coolant gamma isotopic data to predict waste stream-specific 10CFR61 nuclide scaling factors. The code calculates a set of scaling factors for the fuel source nuclides: Sr-90; Pu-241; Tc-99; Cm-242; I-129; and TRU nuclides (see page 2). The code also has pre-calculated scaling factors for C-14 and Ni-63. These scaling factors were developed from industry radiochemistry data. Tritium is not addressed in the code since it will be in the form of tritiated water and does not lend itself to scaling with gamma nuclides. RADSOURCE requires some basic power plant information so the scaling factors developed will be tailored to the plant itself. With these data, the code assesses the reactor core conditions that control the release of the fission products and Transuranics. The code produces estimates of the ratios of the 10CFR61 fission products, listed above and the TRU to Cs-137 ratios released to the reactor. These ratios, become the scaling factors for reactor coolant purification resins. In a separate set of calculations, the code attempts to account for transport and removal into different, specific waste streams, and develops scaling factors based on the levels of radionuclides calculated in the purification resins. A key assumption in this code is that the transport and removal is consistent for each waste stream in all power plants. This code was validated by comparing the purification resin scaling factors produced with scaling factors derived from small test resin columns taken from reactor coolant sampling streams in a mix of 16 PWRs and BWRs.
机译:Radsource是一种微型计算机程序,分析反应器冷却剂γ同位素数据,以预测废物流特异性的10CFR61核素缩放因子。代码计算燃料源核素的一组缩放因子:SR-90; PU-241; TC-99; CM-242; I-129;和tru核素(见第2页)。该代码还具有用于C-14和NI-63的预先计算的缩放因子。这些缩放因子是从工业放射化学数据开发的。代码中未解决氚,因为它将采用氚化水的形式,并且不含有伽马核素的缩放。 Radsource需要一些基本的电厂信息,因此开发的缩放因子将根据植物本身量身定制。通过这些数据,代码评估控制裂变产品和经阵挛的释放的反应堆核心条件。该代码产生10CFR61裂变产物的比率的估计,上面列出的并且TRU至CS-137比率释放到反应器中。这些比率是反应堆冷却剂纯化树脂的缩放因子。在单独的计算集中,代码试图考虑运输和去除在不同,特定的废物流中,并基于在纯化树脂中计算的放射性核素水平来发展缩放因子。该代码中的一个关键假设是传输和拆卸对于所有发电厂中的每个废物流是一致的。通过比较从来自反应器冷却剂采样流的小型测试树脂柱衍生的缩放因子产生的净化树脂缩放因子进行验证,验证了该代码,以16pwrs和bwrs的混合物。

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