Preliminary analysis of fusion-fission hybrid reactor safety

  • Yican Wu
  • , Qunying Huang
  • , Lijian Qiu

Research output: Contribution to journalArticlepeer-review

1 Scopus citations

Abstract

FDKR code was modified on the basis of DKR code which can calculate the radioactivity of fusion reactor. The radioactivity during operation and the potential of radiowastes generated by the reference uranium-plutonium fuel cycle in fusion-fission hybrid reactor was carried out using an improved FDKR code. The computational results were analyzed and compared with those generated by the PWR(U), HTGR and LMFBR. The results show that the safety of hybrid reactor can be compared with that of fission reactor. However, an overall statistical safety assessment is still needed.

Original languageEnglish
Pages (from-to)34-39
Number of pages6
JournalHedongli Gongcheng/Nuclear Power Engineering
Volume15
Issue number1
StatePublished - Feb 1994

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