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All Journal Jurnal Teknologi Reaktor Nuklir Tri Dasa Mega Urania Jurnal Ilmiah Daur Bahan Bakar Nuklir Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir
Kuat Heriyanto
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Energy Materials Science & Nanotechnology

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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 Pungky Ayu Artiani; Yuli Purwanto; Aisyah Aisyah; Ratiko Ratiko; Jaka Rachmadetin; Kuat Heriyanto
JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA Vol 23, No 3 (2021): October (2021)
Publisher : Pusat Teknologi Dan Keselamatan Reaktor Nuklir (PTKRN)

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/tdm.2021.23.3.6355

Abstract

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.
PENGARUH KONDISI PENYIMPANAN TERHADAP KETAHANAN KOROSI DRUM BAJA KARBON WADAH LIMBAH RADIOAKTIF Ibnu Saputra, Dwi Luhur; Aisyah, Aisyah; Setiawan, Risdiyana; Artiani, Pungky Ayu; Heriyanto, Kuat; Rachmadetin, Jaka
Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol 29, No 1 (2023): APRIL, 2023
Publisher : website

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/urania.2023.29.1.6770

Abstract

Instalasi pengelolaan Limbah Radioaktif (IPLR) yang berlokasi di Kawasan Nuklir Serpong merupakan satu satunya fasilitas pengelolaan limbah radioaktif yang telah mengelola limbah radioaktif dari seluruh wilayah Indonesia. Berbagai jenis limbah telah diolah di fasilitas ini antara lain limbah padat material terkontaminasi tingkat rendah maupun sedang yang menggunakan wadah drum baja karbon. Sebagai wadah limbah radioaktif drum wadah limbah ini harus memiliki ketahanan korosi yang baik sehingga drum wadah limbah mampu bertahan dalam jangka penyimpanan yang panjang. Telah dilakukan penelitian tentang korosi baja karbon wadah limbah radioaktif dengan tujuan mendapatkan data laju korosi bahan yang mengalami pengelasan maupun logam induknya pada kondisi penyimpanan lestari. Pada penyimpanan lestari dimungkinkan adanya genangan air yang masuk ke dalam fasilitas penyimpanan sehingga akan berinteraksi dengan drum dan dapat meningkatkan laju korosinya. Pada penelitian ini diukur laju korosi dalam berbagai media pengkorosi yaitu air SP4, air demin, air semen dan air bentonite. Hasil penelitian menunjukkan bahwa laju korosi drum wadah limbah yang mengalami pengelasan lebih tinggi dari laju korosi logam induknya pada berbagai media pengkorosi. Laju korosi tertinggi didapat pada media air SP4 yaitu 7,86 dan 6,78 kalinya dibandingkan dengan air demin. Sedangkan laju korosi pada media air demin, air bentonite dan air semen pada kisaran yang tidak jauh berbeda satu sama lain. Laju korosi merupakan parameter wadah limbah radioaktif yang penting untuk diperhatikan, karena drum wadah limbah dengan ketahanan korosi yang tinggi akan mampu menahan radionuklida yang tersimpan didalamnya dalam jangka waktu yang panjang.Kata kunci: Limbah radioaktif, baja karbon, pengelasan, korosi.
Analisis Kritikalitas Bahan Bakar Nuklir Bekas Reaktor RSG-GAS Pada Rak Berbahan Aluminium Artiani, Pungky Ayu; Mirawaty, Mirawaty; Heriyanto, Kuat
Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol 23, No 2 (2017): Juni 2017
Publisher : website

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (784.828 KB) | DOI: 10.17146/urania.2017.23.2.3280

Abstract

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: kritikalitas, penyimpanan BBNB, rak aluminium, bahan bakar nuklir bekas.
PENGARUH KONDISI PENYIMPANAN TERHADAP KETAHANAN KOROSI DRUM BAJA KARBON WADAH LIMBAH RADIOAKTIF Dwi Luhur Ibnu Saputra; Aisyah Aisyah; Risdiyana Setiawan; Pungky Ayu Artiani; Kuat Heriyanto; Jaka Rachmadetin
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 29 No. 1 (2023): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir
Publisher : Badan Riset dan Inovasi Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/urania.2023.29.1.6770

Abstract

The Radioactive Waste Management Installation (IPLR) in the Serpong Nuclear Area is Indonesia’s only radioactive waste management facility. This facility has treated various types of waste using carbon steel containers, including low and medium-contamination solid waste. Radioactive waste containers must have good corrosion resistance so that the waste container can survive a long storage period. Research on the corrosion of carbon steel radioactive waste containers has been carried out. This study aims to obtain data on the corrosion rate of welded materials radioactive waste container and their parent metals under disposal conditions. In the disposal facility, there is a potential for water seeps in so that the interaction with the waste container may occurred. This condition will increase the corrosion rate. In this study measured the corrosion rate in various corrosion media, namely SP4 water, demineralization water, cemented solution, and bentonite solution. The results showed that the corrosion rate of the welded container was higher than the corrosion rate of its parent metal in various corrosion media. The highest corrosion rate is SP4 water media, which is 7.86 and 6.78 times compared to demineralization water. Meanwhile, the corrosion rate in demineralization water media, bentonite water, and cement water is not significantly different. The corrosion rate is an essential parameter of radioactive waste containers because waste containers with high corrosion resistance will be able to confine radionuclides for a long period time.
ANALISIS KRITIKALITAS BAHAN BAKAR NUKLIR BEKAS REAKTOR RSG-GAS PADA RAK BERBAHAN ALUMINIUM Pungky Ayu Artiani; Mirawaty Mirawaty; Kuat Heriyanto
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 23 No. 2 (2017): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir
Publisher : Badan Riset dan Inovasi Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/urania.2017.23.2.3280

Abstract

The use of stainless steel in nuclear spent fuels storage racks of interim storage facility potentially causes galvanic corrosion so material replacement of spent fuels storage racks needs to be considered. Galvanic corrosion is due to interaction between aluminum as in nuclear fuel of Multipurpose Research Reactor - G. A. Siwabessy (RSG-GAS reactor) and stainless steel as storage rack material for nuclear spent fuel. The purpose of this study is to assess the criticality of nuclear spent fuel storage racks using aluminum material to reduce galvanic corrosion effect. criticality guarantee is necessary to maintain the safety of nuclear spent fuel interim storage facility. Optimum criticality of aluminum storage rack is assessed by varying pitch size and calculating neutron absorption rate performed under normal condition (not an accident). Criticality (keff) calculation is performed using Monte Carlo N-Particle version 6 (MCNP6) code. The model used in this study is a 3-dimensional model where racks are filled fully with spent fuels in the storage pool. The calculations show that nuclear spent fuel storage rack stainless steel materials (keff = 0.6810) compared to aluminum (keff = 0.7709) in the size of 127 mm pitch, keff increased by 13.20%, but still within the value of safety requirement (keff ≤ 0.95). keff is affected by pitch size, where the reduction in the size of 1 mm pitch can increase the keffof 14.24%. Neutron absorption rate also affects keff, where neutron absorption rate in aluminum storage racks smaller than stainless steel. Storage racks using aluminum materials meet safety aspect to use as a storage rack in nuclear spent fuel interim storage facility because it has a keff less than 0.95 on a pitch size more than 112 mm (keff = 0.9196).
EVALUATION OF NEUTRON SHIELDING PERFORMANCE OF CD-SS 316L AS A CANDIDATE ALLOY FOR DRY CASK OF RESEARCH REACTOR SPENT FUEL Kuat Heriyanto; Usman Sudjadi; Jaka Rachmadetin; Yuli Purwanto; Pungky Ayu Artiani; Siti Chotijah
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 27 No. 2 (2021): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir
Publisher : Badan Riset dan Inovasi Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/urania.2021.27.2.6426

Abstract

Development of dry casks is necessary to support national strategy for the management of spent fuels. One of the requirements for the dry cask is shielding performance for neutrons emitted by the spent fuels. The objectives of this study were to determine the emitted neutrons by the spent fuels generated from GAS research reactor and to evaluate the neutron shielding performance of Cd-SS316L alloy as a candidate material to be used for dry cask for the spent fuels. The determination of the emitted neutrons was carried out using Origen 2.1 software while the evaluation of the neutron shielding performance was done using MCNP5. The result shows that the emitted neutrons by a spent fuel after 5 years discharged from GAS research reactor are 2.81×103 and 3.32×106 n/s for reactor core power of 15 and 30 MW, respectively. Addition of Cd improves the neutron shielding performance of SS 316L. It can be concluded that evaluation of neutron shielding performance of Cd-SS316L can be done using Origen 2.1 software for the neutron emission determination and MNCP 5 software for the neutron shielding performance by simulation. This study shows that the Cd-SS 316L alloy is worth further study to develop the dry cask design for the GAS research reactor
PENGARUH IRADIASI GAMMA TERHADAP KARAKTERISTIK POLIMER POLIESTER TAK JENUH UNTUK APLIKASI SOLIDIFIKASI LIMBAH RADIOAKTIF Risdiyana Setiawan; Purwantiningsih Sugita; Muhammad Farid; Ratiko; Jaka Rachmadetin; Kuat Heriyanto; Yuli Purwanto; Dwi Luhur Ibnu Saputra; Andry Setiawan
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 30 No. 2 (2024): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir
Publisher : Badan Riset dan Inovasi Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/urania.2024.9131

Abstract

The first effort in radioactive waste management is through radioactive waste characterization by identifying nuclides and measuring radioactivity. Characterization of radioactive waste is helpful in waste management consisting of waste containment, waste decomposition, temporary waste storage, and disposal operations. The use of polyester polymers in radioactive waste solidification is one of the important solutions in safe and sustainable waste management. These polymers are chosen for their good mechanical and chemical properties, such as resistance to degradation and long-term stability. This study aims to characterize and analyze the effect of gamma irradiation on the mechanical and chemical properties of unsaturated polyester polymers used in radioactive waste solidification. Irradiation was carried out with dose variations of 50, 100, 200, and 300 kGy. The results showed that at low to medium doses (50-200 kGy), there was an increase in compressive strength and density due to the formation of crosslinks between polymer chains. However, at higher irradiation doses (300 kGy), material degradation occurred leading to a decrease in strength. Raman spectrophotometry and SEM showed changes in chemical structure and morphology due to irradiation, especially in terms of changes in functional groups and structural density. The results of this study indicate that irradiation can strengthen polymers at certain doses, but dose limits must be considered to prevent material degradation.
Co-Authors Aisyah Aisyah Aisyah Aisyah Andry Setiawan Artiani, Pungky Ayu Dwi Luhur Ibnu Saputra Ibnu Saputra, Dwi Luhur Jaka Rachmadetin Jaka Rachmadetin Mirawaty Mirawaty Mirawaty, Mirawaty Muhammad Farid Pungky Ayu Artiani Pungky Ayu Artiani Purwantiningsih Sugita Ratiko Ratiko Ratiko Risdiyana Setiawan Risdiyana Setiawan, Risdiyana Siti Chotijah Usman Sudjadi Yuli Purwanto