Simulation of the depressurisation occuring at the beginning of a LOCA in a 4-loop PWR

Robbe, Marie-France; Потапов, С.; Tephany, F.

doi:10.1016/s0029-5493(03)00076-1

Cited by 9 publications

(3 citation statements)

References 7 publications

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“…Skema Sistem Pendingin PWR Sumber: Kukita dkk. (1990); Robbe (2003) 1. SEKUENSI DAN FENOMENA TERMOHIDRAULIKA SELAMA LOCA Fungsi keselamatan pendinginan tidak hanya diperlukan saat reaktor beroperasi, tetapi juga beberapa saat setelah reaktor berhenti beroperasi (shutdown).…”

Section: Kecelakaan Kehilangan Air Pendingin (Loca)unclassified

Keselamatan Reaktor Nuklir: Kecelakaan Dasar Desain dan Kecelakaan Parah

Antariksawan¹,

Juarsa²

2023

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Pembangkit Listrik Tenaga Nuklir (PLTN) telah memberikan kontribusi yang siginifikan pada pembangkitan energi dunia. Meskipun demikian, pertanyaan tentang keselamatan PLTN masih menjadi perdebatan. Tiga kecelakaan terburuk pada PLTN komersial yang terjadi dalam sejarah dunia, yaitu kecelakaan PLTN Three Mile Island unit 2 di Amerika Serikat, PLTN Chernobyl unit 4 di Ukraina, dan PLTN Fukushima Dai-ichi unit 1–4 di Jepang, menjadi salah satu subjek debat tentang keselamatan reaktor nuklir. Di sisi lain, ketiga kecelakaan tersebut juga menjadi dasar dari perbaikan keselamatan PLTN. Kecelakaan-kecelakaan tersebut telah mendorong dilakukannya banyak penelitian dalam rangka melakukan perbaikan dan mengevaluasi standar keselamatan PLTN. Buku ini menjelaskan apa yang terjadi pada ketiga kecelakaan tersebut dan upaya perbaikan melalui riset yang dilakukan serta hasil-hasilnya, terutama yang dilakukan oleh penulis. Pembahasan berfokus pada kecelakaan dasar desain dan kecelakaan parah seperti yang terjadi pada ketiga reaktor nuklir di atas. Lingkup pembahasan buku ini adalah kecelakaan pada reaktor berbasis air ringan, khususnya pada reaktor air bertekanan (pressurized water reactor, PWR). Dari aspek keilmuan, buku ini membahas kecelakaan reaktor nuklir dari sisi keilmuan termohidraulika. Buku ini sangat tepat dibaca bagi mahasiswa, dosen, peneliti, praktisi, serta masyarakat pemerhati nuklir. Buku ini diharapkan dapat memberikan pengetahuan tentang keselamatan reaktor nuklir dengan contoh kecelakaan PLTN dan hasil-hasil riset terkait kecelakaan PLTN.

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Section: Kecelakaan Kehilangan Air Pendingin (Loca)unclassified

Keselamatan Reaktor Nuklir: Kecelakaan Dasar Desain dan Kecelakaan Parah

Antariksawan¹,

Juarsa²

2023

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“…3 by Krieg et al 1977, and later on by Hosford et al 1981 (USNRC NUREG-0609). The depressurization wave, depending upon its amplitude and the upon subcooling of the encountered fluid, may generate voids with a delay of the order of ms after its passage, and it causes complex Fluid Structure Interaction (FSI), as partly discussed by Robbe et al 2003, andMahmoodi et al 2019. FSI is affected by void and by motion of internals (see also Fig.…”

Section: Depressurization Wave Induced Loadsmentioning

confidence: 99%

The technological challenge for current generation nuclear reactors

D'Auria¹,

Debrecin²,

Glaeser³

2019

NUCET

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The present paper deals with the proposal of an additional safety barrier for the class of large (1000 MWe or more) Light Water Reactors (LWR) now in operation, in construction, or under design. Emphasis is given to the motivations or the needs for the barrier. Two main parts of the paper can be distinguished. The following topics are discussed in the former part (section 2): (a) the weakness of the barrier constituted by the current design of nuclear fuel; (b) the continuously increasing complexity of the system, with main reference to the Instrumentation and Control (I&C); (c) the role that the Large Break Loss of Coolant Accident (LBLOCA) had for arriving at the current layout of the Reactor Coolant System (RCS). Furthermore avoiding the severe accidents in 1979, 1987 and 2011, is at the basis of the proposal. In the latter part (sections 3 and 4), the elements of the proposed technological safety barrier are discussed: the As-Low-As-Reasonably-Achievable (ALARA) principle, the Best Estimate Plus Uncertainty (BEPU) approach, the Extended Safety Margin Detection (E-SMD) hardware, the Emergency Rescue Team (ERT) strategy (or a virtual entity for the reactor) and the Independent Assessment (IA) concept. The additional safety barrier, although not demonstrated in the paper, is expected to reduce for a factor in the range 10–1000 the probability of core melt and to have a cost in the order of 1% the cost of a nuclear reactor unit.

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“…Greek letters α force-state parameter β temporal integration factor ε θ thermal elongation of steel η inelastic reduction factor θ nodal temperaturė θ nodal temperature rate θ g gas temperature Θ i , Θ j beam-column end rotations λ n thermal conductivity of the steel µ s coefficient of heat transfer υ s steel specific heat ρ axial load ratio ρ s unit mass of steel σ y yield strength cluding the application of analytical (Hosemann et al, 1984) and sophisticated numerical techniques based on the finite element method (FEM) (Gruner et al, 1985;Robbe et al, 2003). During an accident resulting from a loss-of-coolant accident (LOCA) for instance, containment structures may experience load combinations beyond their design limit.…”

Section: Introductionmentioning

confidence: 99%