Abstract Nuclear fissile material was analyzed for the waste produced in the pyro-process. Nuclear waste is produced at each stage in the pyro-process, spent fuel head-end, major group recovery area and TRU-RE process. Each yields waste of different material composition and properties. Chemical analysis is basically determined for the measurement of nuclear material content. However, the possibility of non-destructive analysis techniques were examined as an additional and supplementary way for cost effectiveness and time saving in the nuclear material analysis. Examinations were undertaken on RE-salt waste, anode sludge, and hull. A gamma peak of Cm244 and Pu239 was simulated for the RE waste. The peak was well distinguishable in the waste. The linearity in the gamma measurement was approved with the content increase in the plutonium isotope. For fissile assay in anode sludge and hull, a neutron method was suggested. From the simulation results, a probable technique was recommended for plutonium content assay in each waste of the pyro-process. An accurate fissile assay will contribute to an increased safeguards for the pyro-processing system and international credibility for the reuse of fissile materials in the fuel cycle.

中文翻译：

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高温处理废物的核测量

摘要 分析了核裂变材料在高温分解过程中产生的废物。核废料在火法工艺、乏燃料头端、主要群体回收区和 TRU-RE 工艺的每个阶段都会产生。每一种都会产生不同材料成分和特性的废物。化学分析基本上确定用于测量核材料含量。然而，无损分析技术的可能性被视为核材料分析中成本效益和节省时间的附加和补充方式。对再生盐废物、阳极污泥和船体进行了检查。模拟了 RE 废物的 Cm244 和 Pu239 的伽马峰。峰在废物中很好区分。随着钚同位素含量的增加，伽马测量的线性得到认可。对于阳极污泥和船体中的裂变分析，建议采用中子法。从模拟结果中，推荐了一种可能的技术用于火法工艺中每种废物中的钚含量测定。准确的裂变分析将有助于加强对高温处理系统的保障和在燃料循环中再利用裂变材料的国际可信度。