1995
DOI: 10.1016/0149-1970(95)00068-u
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A concept and safety characteristics of JAERI passive safety reactor (JPSR)

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Cited by 14 publications
(5 citation statements)
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“…The passive safety conception was proposed to improve the safety and reliability of nuclear power plants (NPPs) in the 1980s. The working principle of a passive safety system is to incorporate and use passive safety measures, such as gravity or natural circulation caused by the density difference based on the existing PWR technology to ensure the integrity of the reactors (Schulz, 2006;Juhn et al, 2000). It not only simplifies engineering safety equipment but also reduces the possible malfunction due to staff intervention, thus improving the inherent safety of nuclear power plants.…”
Section: Introductionmentioning
confidence: 99%
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“…The passive safety conception was proposed to improve the safety and reliability of nuclear power plants (NPPs) in the 1980s. The working principle of a passive safety system is to incorporate and use passive safety measures, such as gravity or natural circulation caused by the density difference based on the existing PWR technology to ensure the integrity of the reactors (Schulz, 2006;Juhn et al, 2000). It not only simplifies engineering safety equipment but also reduces the possible malfunction due to staff intervention, thus improving the inherent safety of nuclear power plants.…”
Section: Introductionmentioning
confidence: 99%
“…Among all the problems related to safety, the key is to make sure that the residual heat is efficiently removed (Iwamura et al, 1995). The Fukushima Daiichi nuclear power plant accident demonstrated that in the event of a station blackout (SBO) combined with the failure of an emergency diesel generator, the residual heat in the reactor core could not be removed effectively, thus likely leading to a series of serious consequences, such as the melting of the reactor core and the leaking of radioactive gasses.…”
Section: Introductionmentioning
confidence: 99%
“…It seems that it is due to an insufficient heat transfer modeling in the pool such as the refueling water tank in the MARS calculation. Besides, PRHRSs for other reactors have been developed in the last decade (Iwamura et al [16]; Samoilov et al [17]; Peng et al [18]; Jinling and Yujun [19]; Kusunoki et al [20]; Xinian et al [21]; Carelli et al [22]).…”
Section: Introductionmentioning
confidence: 99%
“…Several groups have proposed PCCSs that provide coolant water tanks attached to the sidewall of the RCV. [3][4][5] Although these proposed PCCSs would increase the seismic integrity due to the underslung installations, the PCCS configurations are complex. The PCCS proposed by Iwamura et al 3) has three cooling loops.…”
Section: Introductionmentioning
confidence: 99%
“…[3][4][5] Although these proposed PCCSs would increase the seismic integrity due to the underslung installations, the PCCS configurations are complex. The PCCS proposed by Iwamura et al 3) has three cooling loops. The PCCS proposed by Dehbi 4) is composed of double pipes and the PCCS designed by Liu et al 5) adopts two cooling loops that have a limited operation period.…”
Section: Introductionmentioning
confidence: 99%