摘要
叙述了一种用于动力堆乏燃料后处理厂首端，测定浸取过的废包壳中残留铀的方法──无源γ能谱法。设计了一种点阵式源项可变模拟废包壳篮。按燃耗３３０００ＭＷｄ／Ｔ（Ｕ），冷却时间３ａ，残留铀量为原始乏燃料０．２％的条件，对废包壳中存在的实际裂变产物γ放射性活度制作了一套模拟源项。在热室中定量测定了局部源项集中、存在格架碎块，以及基质平均密度变化４６．１％的多种情况下的γ射线脉冲高度谱。各种实验方案结果表明，对￣（１３９）Ｃｓ６６１．６ｋｅＶγ射线测定误差好于２５．３％，对￣（１４４）Ｇｅ２１８６ｋｅＶγ射线测定误差好于－１８．６％。由５－１００ｍｍ铅滤波器的实验结果表明，采用３０ｍｍ厚度的铅滤波器，可使２１８６ｋｅＶ与６６１ｋｅＶγ射线峰面积之比大于１％。
A simulated hull monitoring system based on passive γ ray scanning was set-up in K-01 hot-cell,which consists of a simulated hull basket,a collimator system, a 150cm￣3 HPGe detector andan ORTEC919 multichannel buffer-computer system. Six different kinds of experimental set-upto simulate the variations of γ ray source term distribution(partly concentration)and the varia-tions of matrix density(+46.1%). The experimental results show that the biases of peak area isbetter than -25.3% for￣(137)Cs 662 keV γ rays and -18.6% for￣(144)Ce-￣(144)Pr 2186 keV γ rays.The hardeness of pulse height spectrum is demonstrated to show that the peak area ratio of 2186keV to 662 keV varies from 380 to 72 when the thickness of lead filter Varies form 5mm to30mm.Also studied are the design parameters of collimator system.
出处
《原子能科学技术》
EI
CAS
CSCD
北大核心
1994年第1期1-7,共7页
Atomic Energy Science and Technology
