An old issue and a new challenge for nuclear reactor safety

被引:4
作者
D'Auria, F. [1 ]
机构
[1] Univ Pisa, DESTEC GRNSPG, Lgo L Lazzarino 2, I-56100 Pisa, Italy
关键词
large break loss of coolant accident (LBLOCA); nuclear reactor safety (NRS); licensing perspectives; basis for design of water cooled nuclear reactors (WCNR); MULTI-PHYSICS CODE; COMPUTATIONAL ANALYSIS; FUEL RELOCATION; COOLABILITY; DRACCAR; LOCA;
D O I
10.1007/s11708-021-0729-0
中图分类号
TE [石油、天然气工业]; TK [能源与动力工程];
学科分类号
0807 ; 0820 ;
摘要
Nuclear reactor safety (NRS) and the branch accident analysis (AA) constitute proven technologies: these are based on, among the other things, long lasting research and operational experience in the area of water cooled nuclear reactors (WCNR). Large break loss of coolant accident (LBLOCA) has been, so far, the orienting scenario within AA and a basis for the design of reactors. An incomplete vision for those technologies during the last few years is as follows: Progress in fundamentals was stagnant, namely in those countries where the WCNR were designed. Weaknesses became evident, noticeably in relation to nuclear fuel under high burn-up. Best estimate plus uncertainty (BEPU) techniques were perfected and available for application. Electronic and informatics systems were in extensive use and their impact in case of accident becomes more and more un-checked (however, quite irrelevant in case of LBLOCA). The time delay between technological discoveries and applications was becoming longer. The present paper deals with the LBLOCA that is inserted into the above context. Key conclusion is that regulations need suitable modification, rather than lowering the importance and the role of LBLOCA. Moreover, strengths of emergency core cooling system (ECCS) and containment need a tight link.
引用
收藏
页码:854 / 859
页数:6
相关论文
共 13 条
  • [1] Best Estimate Plus Uncertainty (BEPU): Status and perspectives
    D'Auria, F.
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2019, 352
  • [2] Strengthening nuclear reactor safety and analysis
    D'Auria, F.
    Debrecin, N.
    Glaeser, H.
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2017, 324 : 209 - 219
  • [3] D'Auria F., 2019, J ADVANCEMENT SCI EN, V4, P30
  • [4] D'Auria F., 2019, Nucl. Energy Technol, V5, P183, DOI [10.3897/nucet.5.38117, DOI 10.3897/NUCET.5.38117]
  • [5] DRACCAR: A multi-physics code for computational analysis of multi-rod ballooning, coolability and fuel relocation during LOCA transients. Part Two: Overview of modeling capabilities for LOCA
    Glantz, T.
    Taurines, T.
    Belon, S.
    De Luze, O.
    Guillard, G.
    Jacq, F.
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2018, 339 : 202 - 214
  • [6] DRACCAR: A multi-physics code for computational analysis of multi-rod ballooning, coolability and fuel relocation during LOCA transients Part one: General modeling description
    Glantz, T.
    Taurines, T.
    De Luze, O.
    Belon, S.
    Guillard, G.
    Jacq, F.
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2018, 339 : 269 - 285
  • [7] IAEA, 2019, Deterministic Safety Analysis for Nuclear Power Plants-IAEA SSG-2 Revision 1'
  • [8] Experimental study to assess effects of ballooning and fuel relocation on the coolability of fuel rod bundle
    Kim, Jongrok
    Cho, Seok
    Park, Jong-Kuk
    Youn, Young-Jung
    Moon, Sang-Ki
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2018, 332 : 1 - 10
  • [9] The role of nuclear thermal-hydraulics in the licensing of Atucha-II: The LBLOCA
    Mazzantini, Oscar
    Galassi, Giorgio
    D'Auria, Francesco
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2019, 351 : 33 - 59
  • [10] Schneidesch C., 2020, OECD NEA CSNI SPEC M