一种铅-铋合金冷却快堆的高放废物积累量研究

Research on Accumulation of High Level Radioactive Waste for a LBE-cooled Fast Reactor

  • 摘要: 目前商用压水堆积累了大量的长寿命高放废物,放射毒性强,衰变时间漫长,对环境和人类构成了长期威胁,作为6种第四代核能系统堆型中的一种,铅基冷却快堆在减少长寿命高放废物产生方面具有优势。基于此本文提出了一种热功率为300 MW的铅-铋合金冷却快堆设计。利用MCNP程序对反应堆堆芯进行建模并计算了堆芯在寿期初的主要物理参数,详细分析了燃耗过程中长寿命高放核素的积累量,并与一般压水堆长寿命高放核素的积累量进行了比较。结果表明,对主要关心的次锕系核素,铅-铋合金冷却快堆的产生量远小于压水堆的,而长寿命裂变产物的产生量与压水堆的相当。总体来说,铅-铋合金冷却快堆产生的长寿命高放废物总量小于压水堆的,可看出铅-铋合金冷却快堆在减少长寿命高放废物产生方面更具有竞争性。

     

    Abstract: At present, pressurized water reactors (PWRs) have accumulated massive long-lived high level radioactive wastes with high radiotoxicities and long decay half-life, which has long-term effects on environment and people. Since generation Ⅳ nuclear systems, including lead-cooled fast reactor, have advantages in reducing the long-lived high level radioactive wastes, a 300 MW lead-bismuth-cooled fast reactor (LBE-cooled fast reactor) design was proposed in this paper. The main physical parameters of the reactor core were modeled and calculated by using the MCNP code. Then, the accumulation of the long-lived high level radioactive nuclides was analyzed in detail and compared with the accumulation of radioactive nuclides in PWRs. The results show that productions of the minor actinides in LBE-cooled fast reactor are much less than those of PWRs, while the long-lived fission products accumulated in LBE-cooled fast reactor and PWR are almost equivalent. Overall, the total masses of the long-lived high level radioactive wastes in LBE-cooled fast reactor are less than those in PWRs, which suggests that LBE-cooled fast reactor is more competitive than PWR in reducing the long-lived high level radioactive wastes.

     

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