Radiation dose rate distributions of spent fuel dry casks estimated with MAVRIC based on detailed geometry and continuous-energy models

Gao, Yuan; Hughes, Christopher R.; Greulich, Christopher; Tulenko, James; Enqvist, Andreas; Baciak, James E.

doi:10.1016/j.anucene.2018.03.015

Cited by 18 publications

(6 citation statements)

References 8 publications

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“…The main radiation sources that should be considered for the shielding design of a dry storage unit are primary gamma rays emitted from fission products and actinides, gamma rays from Cobalt-60 in the fuel assemblies' structural materials, secondary gamma rays from the radiative capture of neutrons by cask materials, neutrons from subcritical and spontaneous fission and neutrons emitted from ( , n) reaction of fissile material [6].…”

Section: Modeling Of Storage Costsmentioning

confidence: 99%

“…Gao et al [6] used MAVRIC (Monaco with Automated Variation Reduction using Importance Calculations) to compare the dose rate distributions, with high level of detail, of a TN-32 cask, designed by Transnuclear [13], with two geometry models and two cross-section datasets. The study concludes that primary gamma rays contribute to ∼91% of the total dose rate at the side surfaces of the cask and to ∼99% at the top surface.…”

Section: Modeling Of Storage Costsmentioning

confidence: 99%

“…The bundle of 20 fuel assemblies that make up the source inside the cask are then approximated to a cylinder, as described by Figure 6 and Equations (6) and (7). The approximation considers the 24 available slots for fuel assemblies inside the cask, even though 4 of them are left unused.…”

Section: Cost Modelingmentioning

confidence: 99%

“…Dry casks were first used in 1986 at the Surry power plant as a temporary solution until a permanent destination was defined. However, no permanent solution was ever put in practice by the majority of operators [6].…”

Section: Introductionmentioning

confidence: 99%

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A Methodology for Optimizing the Management of Spent Fuel of Nuclear Power Plants Using Dry Storage Casks

Gomes

Saldanha

Alvim

2019

Science and Technology of Nuclear Installations

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The management of spent nuclear fuel assemblies of nuclear reactors is a priority subject among member states of the International Atomic Energy Agency. For the majority of these countries, the destination of such fuel assemblies is a decision that is yet to be made and the “wait-and-see” policy is thus adopted by them. In this case, the irradiated fuel is stored in on-site spent fuel pools until the power plant is decommissioned or, when there is no more racking space in the pool, they are stored in intermediate storage facilities, which can be another pool or dry storage systems, until the final decision is made. The objective of this study is to propose a methodology that, using optimization algorithms, determines the ideal time for removal of the fuel assemblies from the spent fuel pool and to place them into dry casks for intermediate storage. In this scenario, the methodology allows for the optimal dimensioning of the designed spent fuel pools and the casks’ characteristics, thus reducing the final costs for purchasing new Nuclear Power Plants (NPP), as the size and safety features of the pool could be reduced and dry casks, that would be needed anyway after the decommissioning of the plant, could be purchased with optimal costs. To demonstrate the steps involved in the proposed methodology, an example is given, one which uses the Monte Carlo N-Particle code (MCNP) to calculate the shielding requirements for a simplified model of a concrete dry cask. From the given example, it is possible to see that, using real-life data, the proposed methodology can become a valuable tool to help making nuclear energy a more attractive choice costwise.

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Section: Modeling Of Storage Costsmentioning

confidence: 99%

Section: Modeling Of Storage Costsmentioning

confidence: 99%

Section: Cost Modelingmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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A Methodology for Optimizing the Management of Spent Fuel of Nuclear Power Plants Using Dry Storage Casks

Gomes

Saldanha

Alvim

2019

Science and Technology of Nuclear Installations

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“…BBNB mengandung panas peluruhan dan radioaktivitas yang tinggi, sehingga memerlukan pengelolaan yang baik agar selamat bagi manusia dan lingkungan. [5], [9]- [11]. Gambar 1.…”

Section: Pendahuluanunclassified

Pengaruh Perisai Radiasi Pada Penyimpanan Kering Bahan Bakar Nuklir Bekas untuk Reaktor Daya Eksperimental

Artiani

Ratiko

Purwanto

et al. 2019

Jurnal Pengembangan Energi Nuklir

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PENGARUH PERISAI RADIASI PADA PENYIMPANAN KERING BAHAN BAKAR NUKLIR BEKAS UNTUK REAKTOR DAYA EKSPERIMENTAL Di masa mendatang, Badan Tenaga Nuklir Nasional (BATAN) berencana membangun Reaktor Daya Eksperimental (RDE) dengan daya termal 10 MW. RDE merupakan merupakan reaktor suhu tinggi dengan bahan bakar berupa pebble yang teknologinya mirip dengan reaktor HTR-10. Dalam operasional RDE hal yang perlu diperhatikan adalah pengelolaan Bahan Bakar Nuklir Bekas (BBNB). Oleh karena itu, teknologi pengelolaan BBNB HTR-10 dapat digunakan sebagai acuan dalam pengelolaan BBNB reaktor RDE. Pengelolaan BBNB reaktor HTR-10 disimpan dalam tangki penyimpanan dengan sistem kering. Telah dilakukan perhitungan laju dosis pada tangki penyimpanan BBNB di gedung reaktor dan interim storage menggunakan Monte Carlo N-Particle 5 (MCNP-5). Hasil perhitungan laju dosis pada tangki penyimpanan dengan berbagai ketebalan timbal (Pb) berkisar 11,7 – 2,560 x 106 µSv/jam dan 813,06 – 7,146 x 106 µSv/jam masing-masing pada gedung reaktor dan interim storage. Hal ini menunjukkan bahwa ketebalan Pb pada tangki penyimpanan tidak memberikan pengaruh yang signifikan dalam penurunan laju dosis baik pada gedung reaktor maupun interim storage. Penurunan laju dosis akan lebih efektif dengan penambahan Pb pada shielding luar tangki penyimpanan BBNB. Hasil perhitungan laju dosis berkisar 2,560 x 106 – 20,32 µSv/jam dan 7,146 x 106 – 105,58 µSv/jam untuk berbagai ketebalan Pb pada shielding luar tangki penyimpanan BBNB masing-masing di gedung reaktor maupun interim storage. Meskipun nilai laju dosis tidak memenuhi syarat Nilai Batas Dosis (NBD) bagi pekerja radiasi dan masyarakat, namun untuk keselamatan pekerja radiasi penanganan BBNB ini dapat diakomodir dengan konsep As Low As Resonably Achievable (ALARA), memperpanjang waktu peluruhan BBNB dan menfungsikan dinding interim storage sebagai shielding.Kata kunci : Reaktor Daya Eksperimental (RDE), Bahan Bakar Nuklir Bekas (BBNB), laju dosis, perisai radiasi.

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Advancements in shielding materials for spent fuel storage

Tamayo

Thomas

Rico

et al. 2020

Micro and Nanostructured Composite Materials for Neutron Shielding Applications

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Radiation dose rate distributions of spent fuel dry casks estimated with MAVRIC based on detailed geometry and continuous-energy models

Cited by 18 publications

References 8 publications

A Methodology for Optimizing the Management of Spent Fuel of Nuclear Power Plants Using Dry Storage Casks

A Methodology for Optimizing the Management of Spent Fuel of Nuclear Power Plants Using Dry Storage Casks

Pengaruh Perisai Radiasi Pada Penyimpanan Kering Bahan Bakar Nuklir Bekas untuk Reaktor Daya Eksperimental

Advancements in shielding materials for spent fuel storage

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