The fission product poisoning and burnup calculation for IHNI-1 reactor based on coupled codeof MCNP-ORIGEN

Strategic Study of CAE ›› 2012, Vol. 14 ›› Issue (8) : 69 -71.

PDF (952KB)
Strategic Study of CAE ›› 2012, Vol. 14 ›› Issue (8) : 69 -71.

The fission product poisoning and burnup calculation for IHNI-1 reactor based on coupled codeof MCNP-ORIGEN

Author information +
History +
PDF (952KB)

Abstract

To calculate the fission product poisoning and burnup of the reactor accurately, the paper sets up the coupled calculation methods based on MCNP code and ORIGEN2 code and program data translation, cross section revision and date interface codes. Making use of elaborate reactor model to calculate the fission product poisoning and burnup for in-hospital neutron irradiator mark 1 reactor.

Keywords

IHNI-1 / MCNP / ORIGEN2 / burnup

Cite this article

Download citation ▾
null. The fission product poisoning and burnup calculation for IHNI-1 reactor based on coupled codeof MCNP-ORIGEN. Strategic Study of CAE, 2012, 14(8): 69-71 DOI:

登录浏览全文

4963

注册一个新账户 忘记密码

References

AI Summary AI Mindmap
PDF (952KB)

627

Accesses

0

Citation

Detail

Sections
Recommended

AI思维导图

/