模拟废包壳中残留铀含量的有源中子测定  

DETERMINATION OF THE RESIDUAL URANIUM CONTENT IN SIMULANT LEACHED HULLS

作　　者：乔盛忠[1] 朱荣保[1] 郏惠忠 刘亨军[1] 杨留成[1] 唐培家[1] 丁大纯 陈国安[1] 李纪民[1] 朴勇男 贾向军[1] 

机构地区：[1]中国原子能科学研究院

出　　处：《原子能科学技术》1994年第1期8-15,共8页Atomic Energy Science and Technology

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).

关 键 词：中子质询法 废包壳 中子探测器 

分 类 号：TL241[核科学技术—核燃料循环与材料]