DEVELOPMENT OF A PASSIVE REACTOR SHUTDOWN DEVICE FOR PREVENTION OF CORE DISRUPTIVE ACCIDENTS IN FAST REACTORS: PROJECT OVERVIEW AND PRELIMINARY RESULTS

被引:0
|
作者
Morita, Koji [1 ]
Liu, Wei [1 ]
Arima, Tatsumi [1 ]
Arita, Yuji [2 ]
Kawase, Koharu [2 ]
Sato, Isamu [3 ]
Matsuura, Haruaki [3 ]
Sekio, Yoshihiro [4 ]
Sagara, Hiroshi [5 ]
Kawashima, Masatoshi [5 ]
机构
[1] Kyushu Univ, Fukuoka, Japan
[2] Univ Fukui, Tsuruga, Fukui, Japan
[3] Tokyo City Univ, Tokyo, Japan
[4] Japan Atom Energy Agcy, Ibaraki, Japan
[5] Tokyo Inst Technol, Tokyo, Japan
关键词
Sodium-cooled fast reactor; Core disruptive accident; Severe-accident prevention measure; Passive shutdown system; Subassembly type device;
D O I
暂无
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
After the Fukushima NPP accident in 2011, it has become increasingly important for reactor safety design to consider design measures to prevent the occurrence of severe accidents. In this study, a new subassembly-type passive reactor shutdown device is proposed to enhance the diversity and robustness of prevention measures for core disruptive accidents in sodium-cooled fast reactors. The proposed device contains pins with a fuel material that is kept in the solid state during normal operation but melts into the liquid when its temperature exceeds a prescribed value under the accidents. When a ULOF (unprotected loss of flow) or UTOP (unprotected transient overpower) accident occurs, the device can provide large negative reactivity passively by the relocation of liquefied device fuel into the lower plenum region of the pins by gravitation alone in a short time. The reactor, in which part of usual fuel subassemblies is replaced with the proposed devices, becomes subcritical before driver fuels are damaged, even if ULOF or UTOP transient occurs. In the present study, candidate materials for device fuel such as metallic alloy and chloride, optimum device pin structure for liquefied fuel relocation, and nuclear and thermal-hydraulic characteristics of the device-loaded core under accident conditions will be mainly investigated to demonstrate engineering feasibility of the proposed device. This paper describes the project overview and discusses preliminary results on nuclear requirements for negative reactivity to be inserted for reactor shutdown under expected device conditions.
引用
收藏
页数:10
相关论文
共 5 条
  • [1] Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Preliminary Study
    Morita, Koji
    Liu, Wei
    Arima, Tatsumi
    Arita, Yuji
    Sato, Isamu
    Matsuura, Haruaki
    Sekio, Yoshihiro
    Sagara, Hiroshi
    Kawashima, Masatoshi
    JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE, 2023, 9 (02):
  • [2] Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Study on Device Specifications
    Morita, Koji
    Liu, Wei
    Arima, Tatsumi
    Arita, Yuji
    Sato, Isamu
    Matsuura, Haruaki
    Sekio, Yoshihiro
    Sagara, Hiroshi
    Kawashima, Masatoshi
    JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE, 2023, 9 (04):
  • [3] Development and studying the characteristics of the passive device for fast reactor shutdown
    Portyanoj, A.G.
    Serdun', E.N.
    Sorokin, A.P.
    Egorov, V.S.
    Mal'tsev, V.G.
    Atomnaya Energiya, 1999, 86 (01): : 77 - 81
  • [4] STUDY ON EUTECTIC MELTING BEHAVIOR OF CONTROL ROD MATERIALS IN CORE DISRUPTIVE ACCIDENTS OF SODIUM-COOLED FAST REACTORS: (1) PROJECT OVERVIEW AND PROGRESS UNTIL 2018
    Yamano, Hidemasa
    Takai, Toshihide
    Furukawa, Tomohiro
    Kikuchi, Shin
    Emura, Yuki
    Kamiyama, Kenji
    Fukuyama, Hiroyuki
    Higashi, Hideo
    Nishi, Tsuyoshi
    Ohta, Hiromichi
    Liu, Xiaoxing
    Morita, Koji
    Nakamura, Kinya
    PROCEEDINGS OF THE 2020 INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING (ICONE2020), VOL 2, 2020,
  • [5] STUDY ON EUTECTIC MELTING BEHAVIOR OF CONTROL ROD MATERIALS IN CORE DISRUPTIVE ACCIDENTS OF SODIUM-COOLED FAST REACTORS: (1) PROJECT OVERVIEW AND PROGRESS UNTIL 2019
    Yamano, Hidemasa
    Takai, Toshihide
    Furukawa, Tomohiro
    Kikuchi, Shin
    Emura, Yuki
    Kamiyama, Kenji
    Fukuyama, Hiroyuki
    Higashi, Hideo
    Nishi, Tsuyoshi
    Ohta, Hiromichi
    Morita, Koji
    Nakamura, Kinya
    PROCEEDINGS OF 2021 28TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING (ICONE28), VOL 3, 2021,