Nuha Nazilah Sahabudin, Uli Aprilia Mukaromah, W. Andriyanti, Heri Sutanto
Titanium Dioxide (TiO2) thin films have intriguing optical, photocatalytic, and electrical properties and have been investigated for various applications, including solar cells, biomaterials, corrosion-resistant materials, and gas sensor. In this study, TiO2 thin films were deposited on the surface of 316L Stainless Steel to improve its mechanical properties as an implant material. The deposition method used was DC sputtering with variations in deposition times of 30, 60, 90, 120, and 150 minutes. Vickers hardness test and SEM-EDX characterization were carried out to determine the hardness value, elemental composition, and thickness of the TiO2 thin film formed. Based on these tests, it was discovered that the optimal hardness value of316L stainless Steel material was attained at a deposition period of 90 minutes with a hardness value of 170.10 VHN, and the average thickness of the layer formed was ± 119.02 μm.
{"title":"THE EFFECT OF THE DC-SPUTTERING PROCESS ON CHANGES IN THE HARDNESS VALUE AND ELEMENTS COMPOSITION OF BIOCOMPATIBLE STAINLESS STEEL 316L MATERIAL","authors":"Nuha Nazilah Sahabudin, Uli Aprilia Mukaromah, W. Andriyanti, Heri Sutanto","doi":"10.55981/gnd.2023.6834","DOIUrl":"https://doi.org/10.55981/gnd.2023.6834","url":null,"abstract":"Titanium Dioxide (TiO2) thin films have intriguing optical, photocatalytic, and electrical properties and have been investigated for various applications, including solar cells, biomaterials, corrosion-resistant materials, and gas sensor. In this study, TiO2 thin films were deposited on the surface of 316L Stainless Steel to improve its mechanical properties as an implant material. The deposition method used was DC sputtering with variations in deposition times of 30, 60, 90, 120, and 150 minutes. Vickers hardness test and SEM-EDX characterization were carried out to determine the hardness value, elemental composition, and thickness of the TiO2 thin film formed. Based on these tests, it was discovered that the optimal hardness value of316L stainless Steel material was attained at a deposition period of 90 minutes with a hardness value of 170.10 VHN, and the average thickness of the layer formed was ± 119.02 μm.","PeriodicalId":32551,"journal":{"name":"Ganendra Majalah IPTEK Nuklir","volume":"2 3","pages":""},"PeriodicalIF":0.0,"publicationDate":"2024-03-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140243450","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
S. Suhartono, Noor Anis Kundari, M. Romli, Sumarbagiono Sumarbagiono
{"title":"PENENTUAN TINGKAT KLIERENS LIMBAH RADIOAKTIF HASIL SEMENTASI KONSENTRAT EVAPORASI DAN TINJAUAN KESELAMATAN PEMBUANGANNYA","authors":"S. Suhartono, Noor Anis Kundari, M. Romli, Sumarbagiono Sumarbagiono","doi":"10.55981/gnd.2023.6839","DOIUrl":"https://doi.org/10.55981/gnd.2023.6839","url":null,"abstract":"","PeriodicalId":32551,"journal":{"name":"Ganendra Majalah IPTEK Nuklir","volume":"2001 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2024-03-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140246531","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
During light water reactor severe accident, source terms may interact with structural materials, generating new compounds and affecting their volatility which make the existing codes could not accurately estimate the radioactive release. Cesium is one of the source terms that can interact with structural materials and contributes greatly to the late release phenomenon. Several studies have been conducted to predict the physicochemical interactions between cesium and structural materials. However, the types of chemisorbed cesium compounds onto structural materials are still under discussion. For this reason, this study was carried out using advanced techniques, involving TEM, SEM, EDS and FIB to estimate the chemisorbed cesium compounds onto stainless steel structural material under simulated light water severe accident. This study indicates that cesium is strongly adsorbed on the oxide layer of stainless steel in the form of cesium silica, cesium aluminum silica, and/or cesium ferro silica. CsFeSiO4 and CsAlSiO4 could dominate these compounds.
{"title":"CESIUM CHEMISORPTION ONTO STAINLESS STEEL UNDER SIMULATED LIGHT WATER REACTOR SEVERE ACCIDENT","authors":"Wayan Ngarayana","doi":"10.55981/gnd.2023.6809","DOIUrl":"https://doi.org/10.55981/gnd.2023.6809","url":null,"abstract":"During light water reactor severe accident, source terms may interact with structural materials, generating new compounds and affecting their volatility which make the existing codes could not accurately estimate the radioactive release. Cesium is one of the source terms that can interact with structural materials and contributes greatly to the late release phenomenon. Several studies have been conducted to predict the physicochemical interactions between cesium and structural materials. However, the types of chemisorbed cesium compounds onto structural materials are still under discussion. For this reason, this study was carried out using advanced techniques, involving TEM, SEM, EDS and FIB to estimate the chemisorbed cesium compounds onto stainless steel structural material under simulated light water severe accident. This study indicates that cesium is strongly adsorbed on the oxide layer of stainless steel in the form of cesium silica, cesium aluminum silica, and/or cesium ferro silica. CsFeSiO4 and CsAlSiO4 could dominate these compounds.","PeriodicalId":32551,"journal":{"name":"Ganendra Majalah IPTEK Nuklir","volume":"15 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2024-03-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140246265","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Saefurrochman Saefurrochman, Agus Tri Purwanto, S. R. Adabiah, Sukaryono Sukaryono, Galih Setiaji, Dwi Handoko Arthanto, Karina Anggraeni, Isti Dian Rachmawati, Agus Dwiatmaja, Wijono Wijono, Elin Nuraini, W. Andriyanti, D. Darsono, Andreas Bimo Putro Adjie
An improved design of the conveyor system of Arjuna 1.0 electron accelerator for 3D object irradiation has been done. The penetration of low energy electrons is less than 1 cm in the surface, causing a challenge for the irradiation process for sterilization of 3D objects. We design a conveyor that can be rotated 360o to irradiate objects evenly. The dimension of this conveyor is 1750 x 600 x 800 mm and the maximum diameter of the object is 7 cm. Based on the Frame Bending Stress analysis to calculate the strength of the conveyor frame, it is shown that the maximum displacement is only 0.029 mm, which is very small so it will cause no disturbance to power transfer from the motor to the conveyor. The normal stress (Smax) is 3.926 MPa and the bending stress for Smax (Mx) and Smax (My), are 2.391 MPa and 3.925 MPa respectively. We also calculate the stress analysis of the 3 mm-thickness of the motor mount and found that the Von-Misses Stress, first, and third Principal Stress are 4.425 MPa, 5.01 MPa, and 1.95 MPa respectively. These results confirm that the design and the material used for the conveyor are safe because the stress is very low than the material’s yield strength which is 207 MPa. The power needed for this conveyor is 0.01724 kW, with a maximum speed is 880 rpm. The new model of 3D conveyor has been constructed and can be implemented to ARJUNA 1.0 to irradiate objects on all its surfaces
{"title":"AN IMPROVEMENT OF ARJUNA 1.0 CONVEYOR SYSTEM FOR 3D IRRADIATION","authors":"Saefurrochman Saefurrochman, Agus Tri Purwanto, S. R. Adabiah, Sukaryono Sukaryono, Galih Setiaji, Dwi Handoko Arthanto, Karina Anggraeni, Isti Dian Rachmawati, Agus Dwiatmaja, Wijono Wijono, Elin Nuraini, W. Andriyanti, D. Darsono, Andreas Bimo Putro Adjie","doi":"10.55981/gnd.2023.6826","DOIUrl":"https://doi.org/10.55981/gnd.2023.6826","url":null,"abstract":"An improved design of the conveyor system of Arjuna 1.0 electron accelerator for 3D object irradiation has been done. The penetration of low energy electrons is less than 1 cm in the surface, causing a challenge for the irradiation process for sterilization of 3D objects. We design a conveyor that can be rotated 360o to irradiate objects evenly. The dimension of this conveyor is 1750 x 600 x 800 mm and the maximum diameter of the object is 7 cm. Based on the Frame Bending Stress analysis to calculate the strength of the conveyor frame, it is shown that the maximum displacement is only 0.029 mm, which is very small so it will cause no disturbance to power transfer from the motor to the conveyor. The normal stress (Smax) is 3.926 MPa and the bending stress for Smax (Mx) and Smax (My), are 2.391 MPa and 3.925 MPa respectively. We also calculate the stress analysis of the 3 mm-thickness of the motor mount and found that the Von-Misses Stress, first, and third Principal Stress are 4.425 MPa, 5.01 MPa, and 1.95 MPa respectively. These results confirm that the design and the material used for the conveyor are safe because the stress is very low than the material’s yield strength which is 207 MPa. The power needed for this conveyor is 0.01724 kW, with a maximum speed is 880 rpm. The new model of 3D conveyor has been constructed and can be implemented to ARJUNA 1.0 to irradiate objects on all its surfaces","PeriodicalId":32551,"journal":{"name":"Ganendra Majalah IPTEK Nuklir","volume":"1993 3","pages":""},"PeriodicalIF":0.0,"publicationDate":"2024-03-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140246552","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Ayu Jati Puspitasari, R. Karthika, Puspa Ayu Nugrahani, Widya Febrianti, Nur Rahmah Hidayati
A gamma camera image is produced by a gamma camera that detects the gamma radiation emitted by the radioactive substance or radiopharmaceutical injected into the body. The gamma camera image sometimes has noise that can interfere with the diagnosis. This image is commonly affected by a Poisson-type random noise. This research proposes using a spatial domain filter to study Poisson noise reduction in gamma camera images. The image sample used is the image of a mouse injected with Lu-177-DOTA Trastuzumab with 100 µCi activity detected using a dual-head gamma camera with NaI(Tl) detectors. The grayscale image is treated with Poisson noise, then improved using a spatial domain filter. The spatial domain filters used include Mean, Median, Wiener, and Spatial Lowpass Filters. The mean filter is the best one that can reduce Poisson noise among the four applied filters. The best filter size for noise reduction is 3 with MSE 5.07, PSNR 41.08 dB, and SSIM 0.99.
{"title":"STUDY OF POISSON NOISE REDUCTION ON GAMMA CAMERA IMAGE USING SPATIAL DOMAIN FILTER","authors":"Ayu Jati Puspitasari, R. Karthika, Puspa Ayu Nugrahani, Widya Febrianti, Nur Rahmah Hidayati","doi":"10.55981/gnd.2023.6822","DOIUrl":"https://doi.org/10.55981/gnd.2023.6822","url":null,"abstract":"A gamma camera image is produced by a gamma camera that detects the gamma radiation emitted by the radioactive substance or radiopharmaceutical injected into the body. The gamma camera image sometimes has noise that can interfere with the diagnosis. This image is commonly affected by a Poisson-type random noise. This research proposes using a spatial domain filter to study Poisson noise reduction in gamma camera images. The image sample used is the image of a mouse injected with Lu-177-DOTA Trastuzumab with 100 µCi activity detected using a dual-head gamma camera with NaI(Tl) detectors. The grayscale image is treated with Poisson noise, then improved using a spatial domain filter. The spatial domain filters used include Mean, Median, Wiener, and Spatial Lowpass Filters. The mean filter is the best one that can reduce Poisson noise among the four applied filters. The best filter size for noise reduction is 3 with MSE 5.07, PSNR 41.08 dB, and SSIM 0.99.","PeriodicalId":32551,"journal":{"name":"Ganendra Majalah IPTEK Nuklir","volume":"2004 8","pages":""},"PeriodicalIF":0.0,"publicationDate":"2024-03-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140246494","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Putra Oktavianto, Noor Anis Kundari, A. Saputra, Imam Abdurrosyid, Andri Saputra
SAFETY ANALYSIS TO PREVENT ACCIDENTS IN THE EVAPORATION PROCESS AT EXPERIMENTAL FUEL ELEMENT INSTALLATION WITH THE HAZOPS METHOD. The Experimental Fuel Element Installation (IEBE) DPFK-BRIN has implemented safety standards as a safety reference using Hazard Identification Risk Assessment Determining Control (HIRADC). The HIRADC method has several lacks, so its application is not optimal. In this study, as a complement to the HIRADC method, a risk analysis was carried out using the Hazard and Operability Study (HAZOPS). The hazard identification was carried out during the evaporation process of the uranyl nitrate solution in the E-601 evaporator tank. The HAZOPS method is based on process and instrumentation diagrams (P&ID) to determine the potential hazards during evaporation. It is carried out by determining the nodes and parameters, analyzing deviations from each node or the potential danger of each node, the possible causes of deviations and their consequences, determining the likelihood scale and the level of risk, and making recommendations. Based on the assessment, six nodes were obtained, resulting in 11 deviations caused by 13 equipment malfunctions or failures. The risk assessment of 13 damages resulted in 1 potential low-hazard risk and 12 potential medium-hazard risks. The low-hazard risk category can be overcome by routine handling, such as preventive maintenance and regular equipment calibration. For the medium-hazard risk category, recommendations such as those for the low-hazard risk category and others are necessary to overcome deviations that may occur according to deviation type. According to safety assessment results, it can be concluded that HAZOPS can complement HIRADC to ensure safety is maintained during the process.
{"title":"ANALISIS KESELAMATAN UNTUK MENCEGAH KECELAKAAN PADA PROSES EVAPORASI DI INSTALASI ELEMEN BAKAR EKSPERIMENTAL DENGAN METODE HAZOPS","authors":"Putra Oktavianto, Noor Anis Kundari, A. Saputra, Imam Abdurrosyid, Andri Saputra","doi":"10.55981/gnd.2023.6844","DOIUrl":"https://doi.org/10.55981/gnd.2023.6844","url":null,"abstract":"SAFETY ANALYSIS TO PREVENT ACCIDENTS IN THE EVAPORATION PROCESS AT EXPERIMENTAL FUEL ELEMENT INSTALLATION WITH THE HAZOPS METHOD. The Experimental Fuel Element Installation (IEBE) DPFK-BRIN has implemented safety standards as a safety reference using Hazard Identification Risk Assessment Determining Control (HIRADC). The HIRADC method has several lacks, so its application is not optimal. In this study, as a complement to the HIRADC method, a risk analysis was carried out using the Hazard and Operability Study (HAZOPS). The hazard identification was carried out during the evaporation process of the uranyl nitrate solution in the E-601 evaporator tank. The HAZOPS method is based on process and instrumentation diagrams (P&ID) to determine the potential hazards during evaporation. It is carried out by determining the nodes and parameters, analyzing deviations from each node or the potential danger of each node, the possible causes of deviations and their consequences, determining the likelihood scale and the level of risk, and making recommendations. Based on the assessment, six nodes were obtained, resulting in 11 deviations caused by 13 equipment malfunctions or failures. The risk assessment of 13 damages resulted in 1 potential low-hazard risk and 12 potential medium-hazard risks. The low-hazard risk category can be overcome by routine handling, such as preventive maintenance and regular equipment calibration. For the medium-hazard risk category, recommendations such as those for the low-hazard risk category and others are necessary to overcome deviations that may occur according to deviation type. According to safety assessment results, it can be concluded that HAZOPS can complement HIRADC to ensure safety is maintained during the process.","PeriodicalId":32551,"journal":{"name":"Ganendra Majalah IPTEK Nuklir","volume":"294 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2024-03-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140246921","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2021-11-19DOI: 10.17146/gnd.2021.24.2.6307
R. Tursinah, B. Bunawas, Tri Cahyo, A. Suherman, P. Sukmabuana
In the development of low-medium energy photon calibration facilities we have simulated several types of gamma irradiator collimator materials with ISO 4037-1 design connected to the output beam spectrum and the resulting kerma. Four types of collimator material, namely Al, Fe, Pb, and WCu have been simulated with gamma radiation sources 241Am, 57Co, 137Cs, and 60Co. Simulations were carried out using the Monte Carlo method with the PHITS computer program. Based on the comparison of air kerma produced, collimators made from Al are suitable for gamma sources 241Am, Fe material for gamma sources 57Co, and Pb material for sources 137Cs and 60Co.
{"title":"Effect of Collimator Elements on the Beam Spectrum and KERMA In Gamma Irradiator","authors":"R. Tursinah, B. Bunawas, Tri Cahyo, A. Suherman, P. Sukmabuana","doi":"10.17146/gnd.2021.24.2.6307","DOIUrl":"https://doi.org/10.17146/gnd.2021.24.2.6307","url":null,"abstract":"In the development of low-medium energy photon calibration facilities we have simulated several types of gamma irradiator collimator materials with ISO 4037-1 design connected to the output beam spectrum and the resulting kerma. Four types of collimator material, namely Al, Fe, Pb, and WCu have been simulated with gamma radiation sources 241Am, 57Co, 137Cs, and 60Co. Simulations were carried out using the Monte Carlo method with the PHITS computer program. Based on the comparison of air kerma produced, collimators made from Al are suitable for gamma sources 241Am, Fe material for gamma sources 57Co, and Pb material for sources 137Cs and 60Co.","PeriodicalId":32551,"journal":{"name":"Ganendra Majalah IPTEK Nuklir","volume":"258 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2021-11-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"82107711","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2021-11-19DOI: 10.17146/gnd.2021.24.2.6320
Fajar Sidik Permana, Nazrul Effendy, A. Wardana
{"title":"PERANCANGAN DAN IDENTIFIKASI KENDALI PID PADA ALIRAN HIDROGEN SUMBER ION SIKLOTRON DECY 13","authors":"Fajar Sidik Permana, Nazrul Effendy, A. Wardana","doi":"10.17146/gnd.2021.24.2.6320","DOIUrl":"https://doi.org/10.17146/gnd.2021.24.2.6320","url":null,"abstract":"","PeriodicalId":32551,"journal":{"name":"Ganendra Majalah IPTEK Nuklir","volume":"29 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2021-11-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"75683940","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2021-11-19DOI: 10.17146/gnd.2021.24.2.6241
R. A. P. Dwijayanto, M. Alfarisie
Minor actinides (MA) resulted from nuclear power plants is often considered as nuisance in spent fuel management due to its considerably long half-life. One of available strategies to deal with MA is to incinerate it, in order to reduce its radioactivity. This paper presents a study on MA incineration in RSG-GAS research reactor. Unlike previous study, this work did not separate the MA into individual isotopes, but incinerated as a whole. ORIGEN2.1 code is employed to calculate MA incineration within RSG-GAS core. MA composition used in this study consists of Np, Am, and Cm isotopes. The Central Irradiation Position (CIP) of RSG-GAS is loaded by 6 kg of MA and irradiated for two years. The result shows that about 1 kg of MA were incinerated after two years of irradiation, or 18,87% of the initial concentration. However, the increase of Cm-242 isotope, along with newly-formed Pu isotopes, were found to be significantly increasing short-term radioactivity compared to un-irradiated MA. Thus, two years-worth of MA incineration cannot be considered as effective, and other strategies must be pursued.
核电厂产生的微量锕系元素由于其相当长的半衰期，在乏燃料管理中经常被认为是一个麻烦。处理放射性物质的一种有效策略是将其焚烧，以降低其放射性。本文介绍了在RSG-GAS研究堆中进行MA焚烧的研究。与以前的研究不同，这项工作没有将MA分离成单独的同位素，而是作为一个整体焚烧。采用ORIGEN2.1代码计算RSG-GAS堆芯内的MA焚烧量。本研究中使用的MA组成由Np、Am和Cm同位素组成。RSG-GAS的中心照射位置(CIP)装载6 kg MA，照射2年。结果表明，经过两年的辐照后，约有1kg的MA被焚烧，占初始浓度的18.87%。然而，与未辐照的MA相比，Cm-242同位素的增加以及新形成的Pu同位素显著增加了短期放射性。因此，两年的MA焚烧不能被认为是有效的，必须采取其他策略。
{"title":"Preliminary Study on Minor Actinide Incineration in RSG-GAS without Isotope Separation","authors":"R. A. P. Dwijayanto, M. Alfarisie","doi":"10.17146/gnd.2021.24.2.6241","DOIUrl":"https://doi.org/10.17146/gnd.2021.24.2.6241","url":null,"abstract":"Minor actinides (MA) resulted from nuclear power plants is often considered as nuisance in spent fuel management due to its considerably long half-life. One of available strategies to deal with MA is to incinerate it, in order to reduce its radioactivity. This paper presents a study on MA incineration in RSG-GAS research reactor. Unlike previous study, this work did not separate the MA into individual isotopes, but incinerated as a whole. ORIGEN2.1 code is employed to calculate MA incineration within RSG-GAS core. MA composition used in this study consists of Np, Am, and Cm isotopes. The Central Irradiation Position (CIP) of RSG-GAS is loaded by 6 kg of MA and irradiated for two years. The result shows that about 1 kg of MA were incinerated after two years of irradiation, or 18,87% of the initial concentration. However, the increase of Cm-242 isotope, along with newly-formed Pu isotopes, were found to be significantly increasing short-term radioactivity compared to un-irradiated MA. Thus, two years-worth of MA incineration cannot be considered as effective, and other strategies must be pursued.","PeriodicalId":32551,"journal":{"name":"Ganendra Majalah IPTEK Nuklir","volume":"37 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2021-11-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"74441059","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2021-11-19DOI: 10.17146/gnd.2021.24.2.6280
Ayu Jati Puspitasari, Ika Cismila Ningsih, Muhammad Sulthonur Ridwan, H. Hamadi
The planar scintigraphic image usually has poor resolution and contains noise. This noise can be removed using the coiflet wavelet method so that the image quality gets better. This coiflet wavelet method is a noise reduction method based on frequency analysis. The planar scintigraphy image is the reconstructed image of the gamma radiation count data (phantom with the Cs-137 source in it). The original image is 15×15 pixel. Before the de-noising process, the image went through an interpolation process, which is to increase the pixel size of the image. The original image enlarged to 70×70, 480×480, and 1200×1200 pixel. After de-noising with coiflet wavelet, the image quality is measured based on MSE and PSNR parameters. The resulting images are quite good, with MSE values are close to zero and PSNR values of more than 60 dB. The smaller the MSE and the bigger the PSNR, is getting the better the image quality. In this study, the results show that the 1200×1200 pixel image has the best quality. It means that the image enlargement process has a good effect on the de-noising process, especially if the original image has a low resolution.
{"title":"PLANAR SCINTIGRAPHY IMAGE DE-NOISING USING COIFLET WAVELET","authors":"Ayu Jati Puspitasari, Ika Cismila Ningsih, Muhammad Sulthonur Ridwan, H. Hamadi","doi":"10.17146/gnd.2021.24.2.6280","DOIUrl":"https://doi.org/10.17146/gnd.2021.24.2.6280","url":null,"abstract":"The planar scintigraphic image usually has poor resolution and contains noise. This noise can be removed using the coiflet wavelet method so that the image quality gets better. This coiflet wavelet method is a noise reduction method based on frequency analysis. The planar scintigraphy image is the reconstructed image of the gamma radiation count data (phantom with the Cs-137 source in it). The original image is 15×15 pixel. Before the de-noising process, the image went through an interpolation process, which is to increase the pixel size of the image. The original image enlarged to 70×70, 480×480, and 1200×1200 pixel. After de-noising with coiflet wavelet, the image quality is measured based on MSE and PSNR parameters. The resulting images are quite good, with MSE values are close to zero and PSNR values of more than 60 dB. The smaller the MSE and the bigger the PSNR, is getting the better the image quality. In this study, the results show that the 1200×1200 pixel image has the best quality. It means that the image enlargement process has a good effect on the de-noising process, especially if the original image has a low resolution.","PeriodicalId":32551,"journal":{"name":"Ganendra Majalah IPTEK Nuklir","volume":"26 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2021-11-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"84042353","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
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