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Author:

Yin, Shasha (Yin, Shasha.) | Zhang, Yapei (Zhang, Yapei.) | Tian, Wenxi (Tian, Wenxi.) (Scholars:田文喜) | Qiu, Suizheng (Qiu, Suizheng.) (Scholars:秋穗正) | Su, G. H. (Su, G. H..) | Gao, Xinli (Gao, Xinli.)

Indexed by:

SCIE EI Scopus

Abstract:

Advanced small modular reactors (SMRs) use different design in the systems, structures, components from large reactors for achieving a high level of safety and reliability. In present work, the SMRs severe accident caused by the station blackout (SBO) was modeled and analyzed using MELCOR code, and the simulation of the accident scenario response to SBO was conducted. Based on the steady state calculation, which agrees well with designed values, we introduced the SBO accident for transient calculation. First, the case of the SBO accident without the passive core cooling system (PXS) was calculated. The progression and scenario in the reactor pressure vessel (RPV) and the containment were simulated and analyzed, including the transient response, cooling capacity and thermal-hydraulic characteristics and so on. The station black-out transient in the SMR can be simulated accurately, and the main failure model in the accident process can be concluded. Then three other cases of the SBO accident with different passive safety systems (core makeup tank (CMT), accumulator (ACC), passive residual heat removal system heat exchanger (PRHR HX), automatic depressurization system (ADS)) of the PXS were calculated respectively, and the results for different passive safety systems were compared. The passive core cooling system can not only provide water to the primary coolant system, but also take away the reactor decay residual heat. So in a station black-out transient, we can get more time for restoring AC power, and effectively prevent the accidents such as Fukushima. (C) 2015 Elsevier Ltd. All rights reserved.

Keyword:

MELCOR Severe accident SMR Station black-out

Author Community:

  • [ 1 ] [Yin, Shasha; Zhang, Yapei; Tian, Wenxi; Qiu, Suizheng; Su, G. H.] Xi An Jiao Tong Univ, State Key Lab Multiphase Flow Power Engn, Xian 710049, Peoples R China
  • [ 2 ] [Gao, Xinli] Nucl & Radiat Safety Ctr, Beijing 100082, Peoples R China
  • [ 3 ] [Yin, Shasha]Xi An Jiao Tong Univ, State Key Lab Multiphase Flow Power Engn, Xian 710049, Peoples R China
  • [ 4 ] [Zhang, Yapei]Xi An Jiao Tong Univ, State Key Lab Multiphase Flow Power Engn, Xian 710049, Peoples R China
  • [ 5 ] [Tian, Wenxi]Xi An Jiao Tong Univ, State Key Lab Multiphase Flow Power Engn, Xian 710049, Peoples R China
  • [ 6 ] [Qiu, Suizheng]Xi An Jiao Tong Univ, State Key Lab Multiphase Flow Power Engn, Xian 710049, Peoples R China
  • [ 7 ] [Su, G. H.]Xi An Jiao Tong Univ, State Key Lab Multiphase Flow Power Engn, Xian 710049, Peoples R China
  • [ 8 ] [Gao, Xinli]Nucl & Radiat Safety Ctr, Beijing 100082, Peoples R China

Reprint Author's Address:

  • 秋穗正

    Xi An Jiao Tong Univ, State Key Lab Multiphase Flow Power Engn, Xian 710049, Peoples R China.

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Source :

PROGRESS IN NUCLEAR ENERGY

ISSN: 0149-1970

Year: 2016

Volume: 86

Page: 87-96

1 . 3 1 3

JCR@2016

2 . 2 5 6

JCR@2020

ESI Discipline: ENGINEERING;

ESI HC Threshold:128

JCR Journal Grade:2

CAS Journal Grade:3

Cited Count:

WoS CC Cited Count: 7

SCOPUS Cited Count: 21

ESI Highly Cited Papers on the List: 0 Unfold All

WanFang Cited Count:

Chinese Cited Count:

30 Days PV: 6

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