Integrated blast resistance model of nuclear power plant auxiliary facilities

Irad Brandys, David Ornai, Yigal Ronen

Research output: Contribution to journalArticlepeer-review

2 Scopus citations

Abstract

Standards, guidelines, manuals, and researches refer mainly to the required protection of a nuclear power plant (NPP) containment structure (where the reactor’s vessel is located) against different internal and external extreme events. However, there is no consideration regarding the man-made extreme event of external explosion resulting from air bomb or cruise missile. A novel integrated blast resistance model (IBRM) of NPP’s reinforced concrete (RC) auxiliary facilities due to an external above ground explosion based on two components is suggested. The first is structural dynamic response analysis to the positive phase of an external explosion based on the single degree-of-freedom (SDOF) method combined with spalling and breaching empirical correlations. The second is in-structure shock analysis, resulting from direct-induced ground shock and air-induced ground shock. As a case study, the resistance of Westinghouse commercial NPP AP1000 control room, including a representative equipment, to an external above ground blast loading of Scud B-100 missile at various standoff distances ranging from 250 m (far range) till contact, was analyzed. The structure’s damage level is based on its front wall supports’ angle of rotation and the ductility ratio (dynamic versus elastic midspan displacement ratio). Due to the lack of specific structural damage demands and equipment’s dynamic capacities, common protective structures standards and manuals are used while requiring that no spalling or breaching shall occur in the control room while it remains in the elastic regime. The engineering systems and equipments’ spectral motions should be less than their capacity. The integrated blast resistance model (IBRM) of the structure and its equipment may be used in wider researches concerning other NPP’s auxiliary facilities and systems based upon their specifications.

Original languageEnglish
Article number030903-1
JournalJournal of Nuclear Engineering and Radiation Science
Volume3
Issue number3
DOIs
StatePublished - 1 Jul 2017

ASJC Scopus subject areas

  • Radiation
  • Nuclear Energy and Engineering

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