Preliminary analysis of fusion-fission hybrid reactor safety

Yican Wu; Qunying Huang; Lijian Qiu

Preliminary analysis of fusion-fission hybrid reactor safety

Yican Wu
, Qunying Huang
, Lijian Qiu

能源与动力工程学院

CAS - Institute of Plasma Physics

科研成果: 期刊稿件 › 文章 › 同行评审

1 引用（Scopus）

摘要

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.

源语言	英语
页（从-至）	34-39
页数	6
期刊	Hedongli Gongcheng/Nuclear Power Engineering
卷	15
期	1
出版状态	已出版 - 2月 1994

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引用此

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title = "Preliminary analysis of fusion-fission hybrid reactor safety",

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.",

author = "Yican Wu and Qunying Huang and Lijian Qiu",

year = "1994",

month = feb,

language = "英语",

volume = "15",

pages = "34--39",

journal = "Hedongli Gongcheng/Nuclear Power Engineering",

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number = "1",

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TY - JOUR

T1 - Preliminary analysis of fusion-fission hybrid reactor safety

AU - Wu, Yican

AU - Huang, Qunying

AU - Qiu, Lijian

PY - 1994/2

Y1 - 1994/2

N2 - 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.

AB - 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.

UR - https://www.scopus.com/pages/publications/0028381769

M3 - 文章

AN - SCOPUS:0028381769

SN - 0258-0926

VL - 15

SP - 34

EP - 39

JO - Hedongli Gongcheng/Nuclear Power Engineering

JF - Hedongli Gongcheng/Nuclear Power Engineering

IS - 1

ER -

Preliminary analysis of fusion-fission hybrid reactor safety

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