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Author:

Sun, Hongping (Sun, Hongping.) | Deng, Jian (Deng, Jian.) | 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.) (Scholars:苏光辉)

Indexed by:

EI SCIE Scopus Engineering Village

Abstract:

As the main carrier of fission products, aerosols will transport in the containment and even leak into the environment during accident conditions, resulting in radioactive pollution. Thus, it is of great significance for radiation protection to study the aerosol distribution mitigation measures in containment after severe accidents. A multi-compartment lumped parameter code named ATHROC (Analysis of Thermal Hydraulic Response of Containment) was developed to analyze the thermal–hydraulic behaviors in the containment after accidents for China advance PWR. In order to satisfy the analysis of aerosol behavior in containment, an aerosol module based on the aerosol dynamic and hygroscopic models was added to the code and coupled with spray removal mechanism models. Three different types of benchmark experiments were selected for assessment of the improved code, including CVTR, LACE and CSE tests. Most of the predicted results of thermal–hydraulic responses and aerosol distribution are in realistic agreement with the experimental data. The comparative results show that the code has capabilities to accurately predict the thermal–hydraulic responses during spray activation, aerosol distribution and removal of aerosols by spray droplets. And the problems identified in the code will be further optimized in the future. Currently, the developed improved code satisfies the analysis of aerosol behavior in containment and provides a design for aerosol removal for spray system arrangement. © 2020 Elsevier B.V.

Keyword:

Accidents Aerosols Atmospheric movements Codes (symbols) Fission products Pollution Pressurized water reactors Radiation protection

Author Community:

  • [ 1 ] [Sun, Hongping]Science and Technology on Reactor System Design Technology Laboratory, School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an; 710049, China
  • [ 2 ] [Deng, Jian]Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu; 610041, China
  • [ 3 ] [Zhang, Yapei]Science and Technology on Reactor System Design Technology Laboratory, School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an; 710049, China
  • [ 4 ] [Tian, Wenxi]Science and Technology on Reactor System Design Technology Laboratory, School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an; 710049, China
  • [ 5 ] [Qiu, Suizheng]Science and Technology on Reactor System Design Technology Laboratory, School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an; 710049, China
  • [ 6 ] [Su, G.H.]Science and Technology on Reactor System Design Technology Laboratory, School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an; 710049, China

Reprint Author's Address:

  • [Zhang, Yapei]Science and Technology on Reactor System Design Technology Laboratory, School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an; 710049, China;;

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Source :

Nuclear Engineering and Design

ISSN: 0029-5493

Year: 2020

Volume: 364

1 . 8 6 9

JCR@2020

1 . 8 6 9

JCR@2020

ESI Discipline: ENGINEERING;

ESI HC Threshold:59

CAS Journal Grade:4

Cited Count:

WoS CC Cited Count: 7

SCOPUS Cited Count: 14

ESI Highly Cited Papers on the List: 0 Unfold All

WanFang Cited Count:

Chinese Cited Count:

30 Days PV: 5

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