吉林建筑工程学院学报
吉林建築工程學院學報
길림건축공정학원학보
JOURNAL OF JILIN ARCHITECTURAL AND CIVIL ENGINEERING INSTITUTE
2012年
6期
71-73
,共3页
14MeV中子%MCNP%辐射防护%聚乙烯
14MeV中子%MCNP%輻射防護%聚乙烯
14MeV중자%MCNP%복사방호%취을희
14MeV neutron%MCNP%radiation protection%polytene
在用D—T中子发生器分析煤质时，为了设计14MeV中子防护体，本文先合理简化了实际模型，然后用MC-NP程序对其进行模拟，最后用实验结果修正模拟结果．实验和模拟结果显示，当聚乙烯厚度超过300mm时，地面的中子注量率就达到了辐射防护的要求．为了安全起见，在实际设计中用500mm的聚乙烯防护14MeV中子．
在用D—T中子髮生器分析煤質時，為瞭設計14MeV中子防護體，本文先閤理簡化瞭實際模型，然後用MC-NP程序對其進行模擬，最後用實驗結果脩正模擬結果．實驗和模擬結果顯示，噹聚乙烯厚度超過300mm時，地麵的中子註量率就達到瞭輻射防護的要求．為瞭安全起見，在實際設計中用500mm的聚乙烯防護14MeV中子．
재용D—T중자발생기분석매질시，위료설계14MeV중자방호체，본문선합리간화료실제모형，연후용MC-NP정서대기진행모의，최후용실험결과수정모의결과．실험화모의결과현시，당취을희후도초과300mm시，지면적중자주량솔취체도료복사방호적요구．위료안전기견，재실제설계중용500mm적취을희방호14MeV중자．
When using D - T neutron generator analyzes coal properties, in order to design 14MeV neutron shield, this paper firstly simplifies the actual model reasonably, then uses MCNP program to simulate it. At last, it uses ex-perimental result to revise the simulated result. The experimental result and the simulated result show that the neu-tron fluence rate of ground comes up to the requirement of radiation protection when the thickness of polytene is over 300mm. On the safe side, the polytene which the thickness is 500mm is used to protect 14MeV neutron in the prac-tical design.
