CAJ | 학술논문

利用MCNP程序模拟研究脉冲中子－裂变中子探测铀黄饼，采用脉冲式中子源，利用氦三管中子探测器记录裂变中子，得到铀黄饼中的铀含量信息。通过对14 MeV脉冲中子源和产生的裂变中子在不同铀含量模型中的输运计算，分析了裂变中子与铀含量的关系。结果表明：利用裂变超热中子衰减时间谱，可以确定铀黄饼中的铀含量；通过对热中子衰减时间谱进行校正，可以提高铀黄饼中铀含量计算结果的准确度。
이용MCNP정서모의연구맥충중자－렬변중자탐측유황병，채용맥충식중자원，이용양삼관중자탐측기기록렬변중자，득도유황병중적유함량신식。통과대14 MeV맥충중자원화산생적렬변중자재불동유함량모형중적수운계산，분석료렬변중자여유함량적관계。결과표명：이용렬변초열중자쇠감시간보，가이학정유황병중적유함량；통과대열중자쇠감시간보진행교정，가이제고유황병중유함량계산결과적준학도。
The Monte Carlo N particle transport code ( MCNP ) is used to simulate how to explore the uranium yel?lowcake by using the pulsed neutron?fission neutron ( PNFN) method. In order to obtain uranium yellowcake quan?titation, pulsed neutron source was used, prompt fission neutrons were detected by using the neutron detector. Un?der the condition of different uranium quantitation models, the transport of the 14 MeV pulsed neutron source and the released fission neutron were calculated. On the basis of these, the relationship between fission neutron and ura?nium quantitation was studied. The results show that using the epithermal neutron time decay spectrum, the urani?um yellowcake quantitation can be determined; the precision of the uranium yellowcake quantitation could be in?creased by the correction of thermal neutron time decay spectrum.