摘要
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）。
An equipment,its principle and method are presented,which are used to determine delayedneutrons from residual uranium in hulls interrogated with 14 MeV neutron generated byCockcroft-Walton accelerator.The experimental data and results of simulant leached hulls samplesin reprocessing plant are given in this paper. In the experiment,the neutron yield of the accelera-tor is 3.2 × 10￣9n/s.The sensitivity of the active measurement is 1g￣(235)U/busket.The neutronemission rate from￣(244)Cm spontaneous fission is about 8.92 ×10￣4s￣(-1)/basket hulls if the burn-up ofthe spent fuel assembly is 3.3 × 10￣4 MWd/tU.When residual uranium content is 0.1% of theoriginal uranium content in spent fuel and the measurement time interval is 10 minutes,the preci-sion calculated for residual uranium content would be ±14.4%(2σ).
出处
《原子能科学技术》
EI
CAS
CSCD
北大核心
1994年第1期8-15,共8页
Atomic Energy Science and Technology
关键词
中子质询法
废包壳
中子探测器
Neutron interrogation Leached hull Delayed neutron Neutron detector
