摘要
为开展反应堆屏蔽计算研究,使用NECP-Atlas和NECP-Shield程序,基于我国最新的评价核数据库CENDL-3.2开发了宽群屏蔽数据库NECL-CP29,该数据库的中子能群结构采用基于粒子群算法优化的29群结构。为验证该数据库,使用国际屏蔽基准题库SINBAD中包括Iron-88、ASPIS-NG和HBR-2等在内的屏蔽基准题进行了计算,计算结果不仅与实验测量值进行了比较,而且与国际主流屏蔽数据库BUGLE-B7和BUGLE-96的计算结果进行了对比。验证结果表明,NECL-CP29数据库的计算值与测量值吻合较好,计算精度整体上优于BUGLE-B7和BUGLE-96,且优化的能群结构有效提升了计算效率。
The neutron and photon shielding is an important part of the reactor design for safety of people and facilities.CENDL-3.2 is the latest Chinese evaluated nuclear data library released by China Nuclear Data Center(CNDC)in 2020.Many nuclides were improved with new evaluation techniques and experimental data.Thanks to the high calculation efficiency,broad-group shielding libraries are widely used in shielding calculation.To carry on the research on reactor shielding calculation,the codes NECP-Atlas and NECP-Shield were applied to develop the broad-group shielding library NECL-CP29 based on CENDL-3.2.Generating a broad-group shielding library needs three stages.Firstly,NECL-CP199,a fine-group library with 199 neutron groups and 42 photon groups,was produced using NECP-Atlas and NECP-Shield.When producing the fine-group library,the neutron weight function consists of a 1/E spectrum,a fission spectrum and a thermal Maxwellian spectrum.The photon weight function consists of a 1/E spectrum at the middle energies.At the high and low energy,the spectrum goes down.Secondly,a typical 1D PWR model used in producing BUGLE libraries was calculated using NECL-CP199 to obtain the fine-group flux distribution in the model.Before calculating the model,the nuclides were self-shielded using several different models,including a PWR pin cell model for the core,an iron-water model for the down comer,a concrete model for the concrete,a carbon steel model for the pressure vessel and a stainless-steel model for the baffle and barrel.Lastly,the fine-group fluxes in core,down comer,pressured vessel and concrete were chosen to collapse fine-group cross sections of self-shielded nuclides to generate a broad-group library.Moreover,the fine-group flux in concrete was applied to collapse the fine-group infinite diluted cross sections of all nuclides from NECL-CP199.The energy group structure has an important influence on the accuracy and efficiency for shielding calculation.To obtain an improved broad-group structure for better accuracy and effic
作者
舒文玉
曹良志
SHU Wenyu;CAO Liangzhi(School of Nuclear Science and Technology,Xi’an Jiaotong University,Xi’an,710049,China)
出处
《原子能科学技术》
EI
CAS
CSCD
北大核心
2022年第5期978-987,共10页
Atomic Energy Science and Technology
基金
国家重点研发计划(2017YFE0302200)。
