摘要
选取Pu-238为放射源,采用简化的级联衰变链对其进行源项分析,得到放射源各衰变子体原子数及放射性活度的变化曲线,在此基础上,采用MCNP程序,对放射源进行了精确建模,对放射源辐射场及其有效屏蔽问题进行了模拟计算,得到放射源周围中子、γ能谱及辐射场分布,辐射场计算值与参考实验剂量吻合较好,屏蔽体的采用可有效降低放射源的辐射剂量,其中,γ剂量降低为裸源的0.1%左右,中子剂量降低为裸源的13%～17%。
Calculating the dose around radioactive source by simulation is an important way of radiation analysis and application. It is widely used in engineering. The paper uses a simple decay cascade to analyze the Pu-238 source, and obtains the varying trends of atomic number and activity for the source and its daughters. In view of the above-mentioned situation, it sets up an elab- orate model by MCNP code, calculating the radioactive field and the problem about shield and getting the gamma and neutron en- ergy spectra around the source. The result agrees with the reference, the shield used can reduce the dose effectively. Concretely, the dose of gamma is reduce to about 0.1%, and the neutron, 13%-17%.
出处
《强激光与粒子束》
EI
CAS
CSCD
北大核心
2013年第1期223-226,共4页
High Power Laser and Particle Beams
关键词
MCNP
放射源
剂量
辐射场
屏蔽
MCNP
radioactive source
dose
radiation field
shield
