Reactor cavity cooling system (Rccs) experimental characterization

Capone, Luigi; Hassan, Yassin A.; Vaghetto, Rodolfo

doi:10.1016/j.nucengdes.2011.07.043

Cited by 22 publications

(10 citation statements)

References 5 publications

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“…RDE is an inherently safe nuclear reactor, meaning that the reactor does not need any active safety intervention in the event of a depressurized loss of forced coolant (DLOFC) and pressurized loss of force coolant (PLOFC) [8,9]. The reactor system automatically reverts back to a normal state after the shut-down transient.…”

Section: Theory the Rde Inherent Safetymentioning

confidence: 99%

“…The potential for RCCS failure may be greater in D-LOFC events. Failure modes need to be evaluated since long-term loss of the RCCS cooling function could lead to major RPV and cavity damage, and thus lead to a dependence on other less predictable ultimate heat sinks [15].…”

Section: D-lofc Accident In Htgrmentioning

confidence: 99%

“…As mentioned earlier, the reactor safety systems is implementing defense in depth philosophy, supported by passive safety systems [8]. The latter implies that, even without human intervention, the safety system will perform correctly anyway.…”

Section: Introduction *mentioning

confidence: 99%

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Reactor Cavity Cooling System With Passive Safety Features on Rde: Thermal Analysis During Accident

Kusumastuti

Sriyono²,

Juarsa³

et al. 2019

Tri Dasa Mega

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Reaktor Daya Eksperimental (RDE) is an experimental power reactor based on HTGR technology that implements inherent safety system. Its safety systems are in compliance with "defense in depth" philosophy. RDE is also equipped with reactor cavity cooling system (RCCS) used to remove the heat transferred from the reactor vessel to the containment structure. The RCCS is designed to fulfil this role by maintain the reactor vessel under the maximum allowable temperature during normal operation and protecting the containment structure in the event of failure of all passive cooling systems. The performance and reliability of the RCCS, therefore, are considered as critical factors in determining maximum design power level related to heat removal. RCCS for RDE will use a novel shape to efficiently remove the heat released from the RPV through thermal radiation and natural convection. This paper discusses the calculation of RCCS thermal analysis during accident. The RPV temperature must be maintained below 65ºC. The accident is assumed that there is no electricity from diesel generator supplied to the blower. The methodology used is based on the calculation of mathematical model of the RCCS in the passive mode. The heat is released through cavity by natural convection, in which the RCCS is capable to withdraw the heat at the rate of 50.54 kW per hour.

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Section: Theory the Rde Inherent Safetymentioning

confidence: 99%

Section: D-lofc Accident In Htgrmentioning

confidence: 99%

See 1 more Smart Citation

Reactor Cavity Cooling System With Passive Safety Features on Rde: Thermal Analysis During Accident

Kusumastuti

Sriyono²,

Juarsa³

et al. 2019

Tri Dasa Mega

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“…Hal ini dapat diatasi dengan penambahan pembangkit listrik menggunakan reaktor berpendingin gas helium dengan temperatur tinggi (RGTT). RGTT mempunyai spesifikasi antara lain bahan bakar efisien, limbah nuklir rendah, tahan terhadap penyebaran bahan nuklir berbahaya, energi tahan lama, handal, dan aman dengan adanya reactor cavity cooling system (RCCS) [1][2][3]. Konsep RGTT yang sedang dikembangkan saat ini diberi nama RGTT30 karena didesain dengan daya termal 30 MW th dan temperatur gas helium keluaran teras 700 °C.…”

Section: Pendahuluanunclassified

Desain Awal Turbin Uap Tipe Aksial Untuk Konsep Rgtt30 Berpendingin Helium

Sudadiyo

Pane

2016

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ABSTRAK DESAIN AWAL TURBIN UAP TIPE AKSIAL UNTUK KONSEP RGTT30 BERPENDINGIN HELIUM.Konsep reaktor daya nuklir yang dikembangkan merupakan jenis reaktor berpendingin gas dengan temperatur tinggi (RGTT). Gas yang digunakan untuk mendinginkan teras RGTT adalah helium. Konsep RGTT ini dapat menghasilkan daya termal 30 MW th sehingga dinamakan RGTT30. Temperatur helium mampu mencapai 700 °C ketika keluar dari teras RGTT30 dan digunakan untuk memanaskan air di dalam steam generator hingga mencapai temperatur 435 °C. Steam generator dihubungkan dengan turbin uap yang dikopel dengan generator listrik untuk membangkitkan daya 7,27 MW e . Uap yang keluar dari turbin dilewatkan kondensor untuk mencairkan uap menjadi air. Rangkaian komponen dari steam generator, turbin, dan kondensor dinamakan sistem turbin uap. Turbin terdiri dari sudu-sudu yang dimaksudkan untuk mengubah tenaga uap kedalam tenaga mekanis berupa putaran. Efisiensi turbin merupakan parameter yang harus diperhatikan dalam sistem turbin uap ini. Tujuan dari makalah ini adalah untuk mengusulkan sudu tipe aksial dan untuk menganalisa perbaikan efisiensi turbin. Metode yang digunakan yaitu aplikasi prinsip termodinamika yang berhubungan dengan konservasi energi dan massa. Perangkat lunak Cycle-Tempo dipakai untuk mendapatkan parameter termodinamika dan untuk mensimulasikan sistem turbin uap berbasis RGTT30. Pertama, dibuat skenario dalam simulasi sistem turbin uap untuk mengetahui efisiensi dan laju aliran massa uap yang diperoleh nilai optimal 87,52 % dan 8,759 kg/s pada putaran 3000 rpm. Kemudian, turbin uap diberi sudu tipe aksial dengan diameter tip 1580 mm dan panjang 150 mm. Hasil yang diperoleh adalah nilai efisiensi turbin uap naik menjadi 88,3 % pada putaran konstan (3000 rpm). Penambahan nilai efisiensi turbin sebesar 0,78 % menunjukkan peningkatan kinerja RGTT30 secara keseluruhan.Kata kunci: Tipe aksial, turbin uap, RGTT30 ABSTRACT PRELIMINARY DESIGN ON STEAM TURBINE OF AXIAL TYPE FOR HELIUM-COOLED RGTT30 CONCEPT. The concept of a nuclear power reactor, which evolves, is high temperature gas-cooled reactor type (HTGR). Gas that is used to cool the HTGR core, is helium. The HTGR concept used in this study

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“…A small-scale experimental facility, with a height of 200 mm, was constructed at Texas A&M University representing a half section of a reactor cavity surrounded by water-cooled standpipes (Capone et al, 2011). Measurements were taken of the external surface temperatures of the vessel and standpipes as well as the axial temperature profile in the cavity.…”

Section: Introductionmentioning

confidence: 99%