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New shift-register electronics for improved precision of neutron coincidence and multiplicity assays of plutonium and uranium mass

机译:新的换档电子产品,提高中子巧合的精度和钚和铀质量的多重测定

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Active and passive neutron-coincidence counting (NCC) is used routinely for nondestructive assay (NDA) of uranium and plutonium, in many forms. Passive neutron multiplicity counting (PNMC) is used routinely for NDA of plutonium scrap and waste. We've developed and extensively tested new electronics that significantly improves precision of double and triple coincidences, and multiplicity assays. Using both a time-correlated pulser and neutron sources, we've simulated PNMC assays (PNMAs) for a wide variety of plutonium samples. Plutonium-240-effective masses ranged from 0.1 to 200 g. The important parameter alpha (ratio of (alpha,n) to spontaneous-fission neutrons) varied from 0 to 10. We've also tested one circuit (Fast Accidentals Sampling or FA) on Pu-oxide standards. For sources and standards measurements, representative the majority of NCC and PNMC applications, FA precision reductions relative to conventional multiplicity shift-register (CMSR) circuits, are 20-29percent for doubles, and 24-31percent for multiplicity assays. For ~(240)Pu-effective masses of 50-100 g, FA gains are roughly independent of alpha. For alpha=0, FA gains are roughly independent of ~(240)Pu-effective mass. FA sampling has been implemented in the Advanced Multiplicity Shift Register (AMSR). The AMSR, relative to CMSRs, reduces doubles measurement times by factors of 1.6 to 2.0. The reduction for PNMC assays is by factors of 1.7 to 2.1. Testing of FA sampling on plutonium was done using an integrated system: the Epithermal Neutron Multiplicity Counter (ENMC), the commercial AMSR-150, and the general-purpose international NCC software package, INCC ver. 4.00. FA sampling also significantly improves measurement precision for active NCC assays of uranium. The new electronics reduces the need for high efficiency, and therefore cost, of neutron coincidence and multiplicity counters.
机译:有源和被动中子 - 重合计数(NCC)通常用于铀和钚的非破坏性测定(NDA),以多种形式。被动中子多重性计数(PNMC)通常用于钚废料和废物的NDA。我们开发和广泛地测试了新的电子产品,可显着提高双重和三重重合的精度,以及多种测定。使用时间相关的脉冲和中子源,我们已经模拟了各种钚样品的PNMC测定(PNAMS)。钚-240-有效的质量范围为0.1至200克。重要的参数α((α,n)与自发裂变中子的比率)从0到10之间变化。我们还测试了对PU氧化物标准的一个电路(快速意外采样或FA)。对于来源和标准测量,代表大多数NCC和PNMC应用,相对于传统的多重移位寄存器(CMSR)电路的FA精确降低,为双打20-29%,并且对于多重测定,24-31%。对于〜(240)PU - 有效质量为50-100克,FA收益大致与alpha差别。对于alpha = 0,FA增益大致独立于〜(240)PU有效质量。 FA采样已在高级多重移位寄存器(AMSR)中实现。相对于CMSRS,AMSR可通过1.6至2.0的因素减少双打测量时间。 PNMC测定的还原是通过1.7至2.1的因素。使用综合系统进行钚对钚采样的测试:盖子中子倍数计数器(ENMC),商业AMSR-150,以及通用国际NCC软件包,INCC版。 4.00。 FA采样也显着提高了铀有源NCC测定的测量精度。新电子器件减少了对高效率,因此成本,中子符合和多重计数器的需求。

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