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描述了高压倍加器作为中子源质询废包壳中残留铀含量的缓发中子测定模拟装置的原理及方法，给出了模拟浸取元件包壳样品的实验数据和结果。实验中所采用的加速器中子产额为３．２×１０￣９ｓ＿（－１），测量灵敏度为１ｇ￣（２３５）Ｕ／每篮壳。当乏燃料组件的燃耗为３．３×１０￣４ＭＷｄ／ｔ（Ｕ）时，每篮壳中￣（２４４）Ｃｍ自发裂变的中子发射率为８．９２×１０￣４ｓ＿（－１）。在废包壳中残留铀含量为乏燃料中原始铀含量的０．１％、测量时间为１０ｍｉｎ时，残留铀含量中子计数的测量精度经计算为±１４．４％（２σ）。
The principle and method of high-pressure doubler as a neutron source to simulate the delayed neutron measurement of residual uranium in spent envelop are described. The experimental data and results of simulated enveloping sample are given. The neutron yield of the accelerator used in the experiment was 3.2 × 10 ~ 9s _ (-1) and the sensitivity was 1g ~ (235) U / shell. When the fuel consumption of the spent fuel assembly is 3.3 × 10 ~ 4 MWd / t (U), the spontaneous fission neutron emissivity of ~ (244) Cm per basket is 8.92 × 10 ~ 4s _ (-1) . The residual uranium content in the spent cladding was 0.1% of the original uranium content in the spent fuel and the measurement accuracy of the residual uranium neutron count was calculated to be ± 14.4% (2σ) when the measurement time was 10 min.