Design of serpentine cask for Ghana research reactor-1 spent nuclear fuel

Abrefah, R.G.; Birikorang, S.A.; Nyarko, B.J.B.; Fletcher, J. J.; Akaho, E.H.K.

doi:10.1016/j.pnucene.2014.06.011

Cited by 10 publications

(9 citation statements)

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“…As input, the number of burnup stages and the utilization of secondary libraries were entered. The section also demonstrates how neutron few groups are divided into large groups (Abrefah et al, 2014). After entering all of the required information, the deck was run to generate the ISOTXS le for use in the REBUS-ANL code.…”

Section: Resultsmentioning

confidence: 99%

“…In other words, it splits the number of hours that the reactor operates into sub-intervals based on the reactor's operating time. Using the REBUS-ANL code for HEU and LEU cores at two power levels (full and half power), a simple reactivity rundown was performed to determine the core lifespan of NIRR-1 (Abrefah et al, 2014). A graph of excess reactivity against EFPDs and EHPDs was generated for HEU and LEU cores (Fig.…”

Section: Resultsmentioning

confidence: 99%

“…The speci cation of the external fuel cycle may include reprocessing, and discharged fuel may be recycled back into the reactor. In non-equilibrium cases, the initial composition of the reactor core may be explicitly speci ed, or the core may be loaded from external feeds and discharged fuel recycled back into the reactor, as in equilibrium problems (Abrefah et al, 2014). REBUS-PC can handle both equilibrium and non-equilibrium issues by employing a variety of core geometries, including triangular and hexagonal meshes (Waltar et al, 2011).…”

Section: Group Collapsing and Homogenizationmentioning

confidence: 99%

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Nigerian Research Reactor-1 (NIRR-1) Core Life-time Analysis using Winfrith Improved Multigroup Scheme-Argonne National Lab (WIMS-ANL) and REactor BUrnup System-Argonne National Lab (REBUS-ANL) Computer Code

Balami

2022

Preprint

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The core of the Nigeria Research Reactor-1 has been converted from Highly Enriched Uranium (HEU) fuel to Low Enriched Uranium (LEU); nevertheless, a core lifetime analysis of the converted HEU and current LEU fuel is required. The core lifetime analysis of the NIRR-1 converted HEU and current LEU cores was carried out using the Winfrith Improved Multigroup Scheme-Argonne National Laboratory (WIMS-ANL) and Reactor BUrnup System-Argonne National Laboratory computer codes in this work (REBUS-ANL). One group cross section was generated using the WIMS-ANL. For core lifetime analysis, these group cross sections were employed in the REBUS-ANL programme. A simple reactivity rundown was performed to estimate the core lifetime for HEU and LEU cores at two power levels using the REBUS-ANL code (full and half power). The lifetime of the LEU core was predicted to be approximately 11.91 percent longer than that of the HEU core at full power and 11.81 percent at half power based on the results obtained. This is in good agreement with the value 11 percent reported in the literature, indicating that the selected LEU core can be operated for a longer period of time than the HEU core.

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Section: Resultsmentioning

confidence: 99%

Section: Resultsmentioning

confidence: 99%

Section: Group Collapsing and Homogenizationmentioning

confidence: 99%

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Nigerian Research Reactor-1 (NIRR-1) Core Life-time Analysis using Winfrith Improved Multigroup Scheme-Argonne National Lab (WIMS-ANL) and REactor BUrnup System-Argonne National Lab (REBUS-ANL) Computer Code

Balami

2022

Preprint

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“…Gambar 3 ini akan digunakan sebagai acuan atau dasar untuk melakukan perhitungan nilai K eff . Untuk mendapatkan kondisi yang paling reaktif dalam perhitungan kritikalitas [13], [16], [17] Nilai keff meningkat dengan berkurangnya ukuran pitch, di mana untuk rak stainless steel mengalami kenaikan sebesar 20,88% dan rak aluminium sebesar 22%. Tabel 5 dan Gambar 7 menunjukkan bahwa ukuran pitch 110 mm untuk rak aluminium memberikan nilai keff (0,9655 ± 0,0010) yang melebihi nilai batas keff yang disyaratkan.…”

Section: Metodologiunclassified

Analisis Kritikalitas Bahan Bakar Nuklir Bekas Reaktor RSG-Gas Pada Rak Berbahan Aluminium

Artiani

Mirawaty²,

Heriyanto³

2017

urania

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ABSTRAK ANALISIS SUB-KRITIKALITAS RAK BAHAN BAKAR NUKLIR BEKAS RSG-GAS MENGGUNAKAN ALUMINIUM.Penggunaan stainless steel sebagai material rak penyimpanan bahan bakar nuklir bekas (BBNB) di fasilitas Kanal Hubung -Instalasi Penyimpanan Sementara Bahan Bakar Bekas (KH-IPSB3) berpotensi menyebabkan terjadinya korosi galvanik pada BBNB sehingga penggantian material rak penyimpanan BBNB perlu dipertimbangkan. Potensi korosi galvanik terjadi karena aluminium sebagai material utama kelongsong Bahan Bakar Nuklir (BBN) Reaktor Serba Guna -G. A. Siwabessy (reaktor RSG-GAS) berinteraksi dengan stainless steel sebagai material rak penyimpan BBNB. Aluminium dapat digunakan sebagai material alternatif rak penyimpanan BBNB untuk mengurangi efek korosi galvanik. Penelitian ini bertujuan untuk mengkaji kritikalitas rak penyimpanan BBNB dengan material aluminium. Jaminan kritikalitas diperlukan untuk menjaga keselamatan fasilitas KH-IPSB3. Rak penyimpanan aluminium yang optimum dikaji dengan melakukan simulasi ukuran pitch dan menghitung laju serapan neutron pada kondisi normal (tidak terjadi kecelakaan). Perhitungan nilai kritikalitas (keff) dilakukan menggunakan program Monte Carlo N-Particle versi 6 (MCNP6). Model yang digunakan adalah model 3-dimensi satu rak utuh yang terisi penuh dengan BBNB di dalam kolam penyimpanan. Hasil perhitungan pada ukuran pitch 127 mm menunjukkan bahwa nilai keff rak penyimpanan BBNB dengan material aluminium (keff = 0,7709) lebih besar 13,20% dibandingkan material stainless steel (keff = 0,6810). Nilai keff rak penyimpanan BBNB dengan material aluminium pada ukuran tersebut masih berada dalam rentang yang disyaratkan yaitu keff kurang dari 0,95. Nilai keff dipengaruhi oleh ukuran pitch, dimana dengan berkurangnya ukuran pitch 1 mm dapat meningkatkan nilai keff sebesar 14,24%. Nilai laju serapan neutron juga mempengaruhi nilai keff, di mana laju serap neutron rak penyimpanan dengan material aluminium lebih kecil dibandingkan material stainless steel. Hasil simulasi menunjukkan bahwa rak penyimpanan dengan material aluminium memenuhi aspek keselamatan untuk digunakan sebagai rak penyimpanan BBNB di KH-IPSB3 karena mempunyai nilai keff<0,95 pada ukuran pitch lebih dari 112 mm (keff = 0,9196).Kata kunci: Sub-kritikalitas, penyimpanan BBNB, rak aluminium.

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“…The purpose of this study is to assess the criticality of the dry cask designs to be used for RDNK spent fuel through determination of their k eff values. The values were calculated using MCNP5 program which had already been used in analyzing the criticality both at the nuclear reactor and at the non-nuclear reactor facility [16][17][18][19]. The calculations were performed for the dry cask designs with and without air gaps in normal and abnormal conditions.…”

Section: Introduction mentioning

confidence: 99%

CRITICALITY SAFETY ANALYSIS OF THE DRY CASK DESIGN WITH AIR GAPS FOR RDNK SPENT PEBBLE FUELS STORAGECriticality Safety Analysis of the Dry Cask Design with Air Gaps for RDNK Spent Pebble Fuels Storage

Artiani

Purwanto²,

Aisyah³

et al. 2021

Tri Dasa Mega

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Reaktor Daya Non-Komersial (RDNK) with a 10 MW thermal power has been proposed as one of the technology options for the first nuclear power plant program in Indonesia. The reactor is a High Temperature Gas-Cooled Reactor-type with spherical fuel elements called pebbles. To support this program, it is necessary to prepare dry cask to safely store the spent pebble fuels that will be generated by the RDNK. The dry cask design has been proposed based on the Castor THTR/AVR but modified with air gaps to facilitate decay heat removal. The objective of this study is to evaluate criticality safety through keff value of the proposed dry cask design for the RDNK spent fuel. The keff values were calculated using MCNP5 program for the dry cask with 25, 50, 75, and 100% of canister capacity. The values were calculated for dry casks with and without air gaps in normal, submerged, tumbled, and both tumbled and submerged conditions. The results of calculated keff values for the dry cask with air gaps at 100% of canister capacity from the former to the latter conditions were 0.127, 0.539, 0.123, and 0.539, respectively. These keff values were smaller than the criticality threshold value of 0.95. Therefore, it can be concluded that the dry cask with air gaps design comply the criticality safety criteria in the aforementioned conditions.

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Design of serpentine cask for Ghana research reactor-1 spent nuclear fuel

Cited by 10 publications

References 1 publication

Nigerian Research Reactor-1 (NIRR-1) Core Life-time Analysis using Winfrith Improved Multigroup Scheme-Argonne National Lab (WIMS-ANL) and REactor BUrnup System-Argonne National Lab (REBUS-ANL) Computer Code

Nigerian Research Reactor-1 (NIRR-1) Core Life-time Analysis using Winfrith Improved Multigroup Scheme-Argonne National Lab (WIMS-ANL) and REactor BUrnup System-Argonne National Lab (REBUS-ANL) Computer Code

Analisis Kritikalitas Bahan Bakar Nuklir Bekas Reaktor RSG-Gas Pada Rak Berbahan Aluminium

CRITICALITY SAFETY ANALYSIS OF THE DRY CASK DESIGN WITH AIR GAPS FOR RDNK SPENT PEBBLE FUELS STORAGECriticality Safety Analysis of the Dry Cask Design with Air Gaps for RDNK Spent Pebble Fuels Storage

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