Science and Technology of Nuclear Installations

Science and Technology of Nuclear Installations / 2009 / Article
Special Issue

Passive Safety Systems in Advanced PWRs

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Editorial | Open Access

Volume 2009 |Article ID 643950 | 2 pages | https://doi.org/10.1155/2009/643950

Passive Safety Systems in Advanced PWRs

Received31 Dec 2009
Accepted31 Dec 2009
Published29 Mar 2010

Passive safety systems have been widely applied to advanced water-cooled reactors (WCRs), to enhance the safety of nuclear power plants. For the near term and medium term, the Chinese government decided for advanced pressurized water reactors with an extensive usage of passive safety systems. The International Workshop on Passive Safety Systems of Advanced PWR (IPASS’08) was held in Shanghai on April 28–30, 2008, coorganized by the Shanghai Jiao Tong University and the Pisa University. The main purposes of the Workshop IPASS’08 are (a) to provide a platform to the international nuclear community for exchanging research results and design experience on passive safety systems applied to advanced WCR and (b) to enhance the contact and collaboration between the Chinese research institutions and international partners.

More than 100 scientists and nuclear engineers from eight countries, that is, Canada, China, France, Germany, Italy, Korea, Pakistan, and USA, were participating in this workshop. More than 60 technical papers were presented covering the following topics:

(a)safety injection and decay heat removal systems,(b)passive containment cooling systems and hydrogen safety research,(c)passive systems for severe accident mitigation,(d)assessment and application of numerical tools,(e)single effect and integral verification experiments,

Eight papers were selected for this special issue. The first paper of Cheng et al. [1] gives a summary about the Chinese research activities on passive safety systems of advanced PWR. Experimental studies and validation of numerical codes are presented in the following two papers [2, 3]. The paper of Gou et al. [4] deals with numerical analysis of the performance of passive safety systems; whereas the methodology for the reliability assessment of passive safety systems is investigated in the paper of Pierro et al. [5]. The last three papers are devoted to hydrogen safety issue, which is a main topic of the workshop [68].

The editors of this special issue express thanks to all authors for their contribution.

Cheng Xu
Yanhua Yang
Walter Ambrosini
Dino A. Araneo

References

  1. X. Cheng, Y. H. Yang, Y. Ouyang, and H. X. Miao, “Role of passive safety systems in Chinese nuclear power development,” Science and Technology of Nuclear Installations, vol. 2009, Article ID 573026, 7 pages, 2009. View at: Publisher Site | Google Scholar
  2. M. Carelli, L. Conway, M. Dzodzo et al., “The SPES3 experimental facility design for the IRIS reactor simulation,” Science and Technology of Nuclear Installations, vol. 2009, Article ID 579430, 12 pages, 2009. View at: Publisher Site | Google Scholar
  3. W. Reactors, W. Ambrosini, M. Bucci, N. Forgione, A. Manfredini, and F. Oriolo, “Experiments and modelling techniques for heat and mass transfer in light,” Science and Technology of Nuclear Installations, vol. 2009, Article ID 738480, 11 pages, 2009. View at: Google Scholar
  4. J. Gou, S. Qiu, G. Su, and D. Jia, “Thermal hydraulic analysis of a passive residual heat removal system for an integral pressurized water reactor,” Science and Technology of Nuclear Installations, vol. 2009, Article ID 473795, 12 pages, 2009. View at: Google Scholar
  5. F. Pierro, D. Araneo, G. Galassi, and F. D'Auria, “Application of REPAS methodology to assess the reliability of passive safety systems,” Science and Technology of Nuclear Installations, vol. 2009, Article ID 768947, 18 pages, 2009. View at: Google Scholar
  6. J. Xiong, Y. Yang, and X. Cheng, “CFD application to hydrogen risk analysis and PAR qualification,” Science and Technology of Nuclear Installations, vol. 2009, Article ID 213981, 10 pages, 2009. View at: Publisher Site | Google Scholar
  7. P. Royl, J. R. Travis, W. Breitung, J. Kim, and S. B. Kim, “GASFLOW validation with panda tests from the OECD SETH benchmark covering steam/air and steam/helium/air mixtures,” Science and Technology of Nuclear Installations, vol. 2009, Article ID 759878, 13 pages, 2009. View at: Google Scholar
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Copyright © 2009 Xu Cheng et al. This is an open access article distributed under the Creative Commons Attribution License, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.


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