Calculation chain for the analysis of spent nuclear fuel in long-term interim dry storage

Arkoma, Asko; Huhtanen, Risto; Leppänen, Jaakko; Peltola, Juho; Pättikangas, Timo

doi:10.1016/j.anucene.2018.04.037

Cited by 20 publications

(8 citation statements)

References 18 publications

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“…Penyimpanan tipe kering temperatur kelongsong BBNB tidak boleh melebihi batas yang ditentukan sesuai dengan jenis BBNB masing-masing pada penyimpanan bahan bakar nuklir bekas untuk waktu yang lama [3][4][5]. Jika tidak didinginkan pada temperatur BBNB yang cukup tinggi, kelongsong BBNB berpotensi rusak dan menyebarkan radionuklida yang ada dalam BBNB [3].…”

Section: Pendahuluanunclassified

Pemodelan Dinamik Pendinginan Bahan Bakar Nuklir Bekas Reaktor Riset Secara Natural Konveksi Pada Prototipe Dry Cask Storage

Istavara

Ratiko

Pratama

et al. 2022

urania

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PEMODELAN DINAMIK PENDINGINAN BAHAN BAKAR NUKLIR BEKAS REAKTOR RISET SECARA NATURAL KONVEKSI PADA PROTOTIPE DRY CASK STORAGE. Penelitian ini secara khusus bertujuan untuk menguji kelayakan desain dry cask storage dan secara umum memberikan solusi penyimpanan Bahan Bakar Nuklir Bekas (BBNB) di Indonesia. Karena keterbatasan ruang penyimpanan pada penyimpanan tipe basah, maka penelitian ini bertujuan untuk merancang, melakukan eksperimen dan mensimulasikan secara simultan. Pengujian desain canister memvariasikan tegangan heater 50 V sampai dengan 125 V dengan kondisi tertutup untuk mengetahui respon canister terhadap tegangan yang sebanding dengan panas peluruhan BBNB. Eksperimen dengan menggunakan ventilasi dry cask storage memvariasikan tegangan 100 V sampai dengan 175 V bertujuan untuk menguji dry cask storage terhadap pendinginan canister secara natural konveksi. Perhitungan secara teori dan simulasi menggunakan software juga dilakukan sebagai pembanding hasil dari eksperimen dari segi pendinginan secara natural konveksi dan hambatan termal. Hasil eksperimen menunjukkan respon desain canister berfungsi dengan baik yaitu semakin besar tegangan listrik yang diberikan, maka temperatur canister bertambah tinggi, yaitu 50 V sampai 125 V merespon 33,4°C sampai 56,6°C. Pengujian pendinginan canister secara natural konveksi menunjukkan hasil yang baik, yaitu antara lain dengan metode buka dan tutup ventilasi dry cask menunjukkan penurunan temperatur canister pada tegangan 100 Volt sebesar 16,1°C dan 14,8°C pada 125 Volt. Hasil nilai komparasi antara eksperimen, perhitungan teori dan simulasi pada 175 V temperatur canister yaitu 44,9°C, 49,7°C dan 65°C secara berurutan, untuk air velocity yaitu 0,20 m/s, 0,25 m/s dan 0,39 m/s secara berurutan. Hasil perhitungan teori dan simulasi sedikit lebih tinggi dari eksperimen, ini mungkin disebabkan adanya kehilangan panas ke lingkungan saat eksperimen berlangsung. Hasil simulasi diperoleh kontur temperatur dan perilaku aliran natural konveksi didalam air gap menunjukkan desain dry cask storage berfungsi dengan baik.Kata kunci : Bahan bakar nuklir bekas, natural konveksi, canister, dry cask storage.

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Section: Pendahuluanunclassified

Pemodelan Dinamik Pendinginan Bahan Bakar Nuklir Bekas Reaktor Riset Secara Natural Konveksi Pada Prototipe Dry Cask Storage

Istavara

Ratiko

Pratama

et al. 2022

urania

View full text Add to dashboard Cite

show abstract

“…Second, creep is selflimiting: progressing creep increases the rod volume which decreases RIP, which is the main force driving the cladding creep; as the driving force is lower, the creep rate decreases. Even though creep does not threaten the cladding integrity directly, it affects distribution of stresses [15,28] . The cladding stress is important in predicting the orientation of hydrides in dry storage [53,54] .…”

Section: Long-term Creep Behaviormentioning

confidence: 99%

“…In Finland, the study on dry storage has been done in the frame of the Finnish Research Programme on Nuclear Power Plant Safety SAFIR2014 [125] and SAFIR2018 [126] . A calculation chain for the analysis of SNF under dry storage conditions in Finland has been done at the Research Center of Finland VTT and described by Arkoma et al [15] . In the demonstration case, simulated by the authors, a CASTOR® V/21 cask is filled with 21 PWR fuel assemblies.…”

Section: Finlandmentioning

confidence: 99%

Spent nuclear fuel in dry storage conditions – current trends in fuel performance modeling

Konarski

Cozzo

Khvostov

et al. 2021

Journal of Nuclear Materials

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The role of dry storage in spent nuclear fuel management becomes more and more important. Originally intended to serve as a temporary solution for a few decades until final disposal, now dry storage period is to be extended to 100 years and beyond. It has to be proven for licensing that the fuel rod integrity during dry storage is ensured. Since it is difficult to provide experimental support, the licensing process has to rely largely on numerical simulations. This paper reviews the literature associated with the modeling of spent nuclear fuel under dry storage conditions. The main phenomena threatening the fuel rod integrity and the numerical models representing them are described here. Moreover, the most recent or currently ongoing experimental efforts that could support the modeling of nuclear fuel in dry storage in the future are discussed. Finally, this paper reviews approaches to dry storage modeling chosen by different countries. In general, these approaches are similar and can be described as a calculation chain consisting of neutronics-thermo-hydraulics-fuel performance computations where sensitivity and uncertainty studies are crucial elements.

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“…The real damage of corrosion cracking of fuel element cladding under effect of tensile stress occurring due to release of gaseous fission products is cause for concern [4][5][6]. However, due to the fact that estimates show [7,8] insignificant (only by 0.7%) stress growth in fuel claddings for 40 years of storage, any studies for forecasting the corrosion cracking of fuel element cladding were not carried out. The forecasting of fuel assembly behavior during dry long-term storage can be implemented based on calculated data obtained by computer codes.…”

Section: Introductionmentioning

confidence: 99%

The Forecasting of Corrosion Damage of Structural Materials during Dry Long-Term Storage of RD BN-350 SNF with CC-19 SFA

Koyanbayev

Skakov

Batyrbekov

et al. 2019

Science and Technology of Nuclear Installations

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There are results of long-term thermal aging of samples of irradiated and nonirradiated FA jacket and nonirradiated fuel element cladding at a temperature range from 300 to 550°C in argon, to 600°C in air. Materials have been studied before and after thermal tests. The forecast estimation of expected corrosion damage of barrier material at the radionuclide release from spent fuel assemblies of BN-350 reactor into environment during dry storage for 50 years was carried out.

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Calculation chain for the analysis of spent nuclear fuel in long-term interim dry storage

Cited by 20 publications

References 18 publications

Pemodelan Dinamik Pendinginan Bahan Bakar Nuklir Bekas Reaktor Riset Secara Natural Konveksi Pada Prototipe Dry Cask Storage

Pemodelan Dinamik Pendinginan Bahan Bakar Nuklir Bekas Reaktor Riset Secara Natural Konveksi Pada Prototipe Dry Cask Storage

Spent nuclear fuel in dry storage conditions – current trends in fuel performance modeling

The Forecasting of Corrosion Damage of Structural Materials during Dry Long-Term Storage of RD BN-350 SNF with CC-19 SFA

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