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一次屏蔽计算TORT程序源项生成方法研究 被引量:4

Research on Primary Shielding Calculation Source Generation Method for TORT Code
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摘要 一次屏蔽计算对于评估工作人员的辐射剂量、确保反应堆压力容器(RPV)及堆内构件在整个反应堆寿期内的安全性、防止混凝土屏蔽体及其外部部件和结构被过度活化具有重要意义。本文推导了TORT程序三维源分布计算公式和源几何转换方法,编写了相应的程序模块,并在秦山一期、CAP1400和CAP1700计算模型上进行了验证和应用。结果表明,本文推导的理论模型和开发的程序是正确的,为后续提高一次屏蔽设计精度提供了基础。 The primary shielding calculation plays an important role in evaluating the radiation dose of personnel,insuring the safety of reactor pressure vessel(RPV)and reactor internal component during the whole lifetime,and preventing the concrete shielding as well as the outer component and structure from an excess of activation.In this paper,three-dimensional source distribution calculation formula and source geometry transformation method were studied,and a source term generation code for TORT code was developed.The validation and application of primary shielding calculation model on Qinshan Ⅰ,CAP1400 and CAP1700were performed.The results show that the theoretical model and the code are both correct,which will be used to improve the accuracy of primary shielding calculation.
出处 《原子能科学技术》 EI CAS CSCD 北大核心 2017年第10期1905-1909,共5页 Atomic Energy Science and Technology
关键词 TORT程序 源项生成程序 一次屏蔽 TORT code source generation code primary shielding
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  • 1[1]Engle Jr W.W. ANISN,A One Dimensional Discrete Ordinates Transport Code with Anisotropic Scatterring[R]. K-1693, 1967.
  • 2[2]Rhoades W.A, et. al, DOT3.5 Two Dimensional Discrete Ordinates Radiation Transport Code [R]. CCC -267,1975. 10
  • 3[3]Roussin R.W. BUGLE-80,Coupled 47 Neutron, 20 Gamma-ray, P3, Cross Section Library for LWR Shielding Calculations[R]. RSIC, DLC-75/BUGLE-80,1980.
  • 4[4]Brodkin E. B.et al. Determinatian of Characteristics of the Neutron Field Affecting the WWER Reactor Vessel[C].The 6th Internationnal Conference on Radiation shielding, Tokyo,Japan. 1983.
  • 5[5]Prillinger G, Pfister G. The Necessity of Detailed Multi-Dimensional Transport Calculations in LWR Pressure Vessel Surveillance and MTR Irradia tion[C].The 6th Internationnal Conference on Radiation shielding, Tokyo, Japan. 1983.
  • 6[6]Cogburn C. O, et al, Neutron Dosimetry of PWR Pressure Vessels[C]. Theory and Practices in Radiation Protection and Shielding, Knoxvill, Tennessee, 1987.

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