Pub Date : 2020-10-31DOI: 10.24246/IJPNA.V5I3.76-79
L. Lestari
Coronavirus has become a world pandemic since WHO announced it in March 2020. This study aims to report on the role of radiologic technology in helping to diagnose the Covid-19 disease handled by RSPAW Salatiga. The research method chosen was descriptive-analytic case reports. The results of the study explained that radiologic technology of chest X-Ray was able to provide an image of Covid-19 with 89% sensitivity, namely the discovery of reticulonodular, ground-glass opacity (GGO), crazy paving, consolidation, location in the periphery of the lung, and the inferior lobe of the lung.
{"title":"The Role of Radiologic Technology in Enforcing Diagnosis of Covid-19 Disease: Case Report at RSPAW Salatiga","authors":"L. Lestari","doi":"10.24246/IJPNA.V5I3.76-79","DOIUrl":"https://doi.org/10.24246/IJPNA.V5I3.76-79","url":null,"abstract":"Coronavirus has become a world pandemic since WHO announced it in March 2020. This study aims to report on the role of radiologic technology in helping to diagnose the Covid-19 disease handled by RSPAW Salatiga. The research method chosen was descriptive-analytic case reports. The results of the study explained that radiologic technology of chest X-Ray was able to provide an image of Covid-19 with 89% sensitivity, namely the discovery of reticulonodular, ground-glass opacity (GGO), crazy paving, consolidation, location in the periphery of the lung, and the inferior lobe of the lung.","PeriodicalId":383123,"journal":{"name":"Indonesian Journal of Physics and Nuclear Applications","volume":"45 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2020-10-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"128089303","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 : 2020-10-31DOI: 10.24246/IJPNA.V5I3.80-86
Gabriel Simanjuntak
BNCT is the latest method in nuclear technology that combines chemotherapy and radiotherapy. Therapy that uses ionizing radiation must pay attention to the safety of patients, radiation workers and the environment. Therefore, shielding is needed for radiation protection, especially gamma radiation. A refining for the shielding and the testing had been done to know the limitation for the use of testing facility in vivo / in vitro that meets the NPD/Dose Constraint limitation from PSTA BATAN with parameter shielding radiation outcome, shielding geometry, and energy value Kartini Reactor. The highest measurement result reaches 4.8 mSv/j with 100kW energy. By considering the measurement result with the NPD/Dose Constraint limitation from PSTA BATAN for Kartini Reactor operation, the activity of testing facility in vivo/in vitro can be done 46 times in a year. Keywords : BNCT, Shielding, Gamma Radiation.
{"title":"GAMMA RADIATION ANALYSIS ON IN VIVO/ IN VITRO TESTING FACILITY BORON NEUTRON CAPTURE THERAPY","authors":"Gabriel Simanjuntak","doi":"10.24246/IJPNA.V5I3.80-86","DOIUrl":"https://doi.org/10.24246/IJPNA.V5I3.80-86","url":null,"abstract":"BNCT is the latest method in nuclear technology that combines chemotherapy and radiotherapy. Therapy that uses ionizing radiation must pay attention to the safety of patients, radiation workers and the environment. Therefore, shielding is needed for radiation protection, especially gamma radiation. A refining for the shielding and the testing had been done to know the limitation for the use of testing facility in vivo / in vitro that meets the NPD/Dose Constraint limitation from PSTA BATAN with parameter shielding radiation outcome, shielding geometry, and energy value Kartini Reactor. The highest measurement result reaches 4.8 mSv/j with 100kW energy. By considering the measurement result with the NPD/Dose Constraint limitation from PSTA BATAN for Kartini Reactor operation, the activity of testing facility in vivo/in vitro can be done 46 times in a year. \u0000Keywords : BNCT, Shielding, Gamma Radiation. \u0000 ","PeriodicalId":383123,"journal":{"name":"Indonesian Journal of Physics and Nuclear Applications","volume":"1 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2020-10-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"117245547","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}
This research purpose is to estimate the dose distribution of BNCT in water phantom. Some common methods in the treatment of cancer such as brakhiterapi, surgery, chemotherapy, and radiotherapy still have the risk of damaging healthy tissue around cancer cells. BNCT is a selectively-designed technique by targeting high-loaded LET particles to tumors at the cellular level. BNCT proves to be a powerful method of killing cancer without damaging normal tissue. The source of the neutron used from the cyclotron dose in water phantom with the size of 30 cm x 30 cm x 30 cm was calculated using PHITS program. The result from the simulation is that boron water panthom has a dosimetri higher than phantom water without boron.
本研究的目的是估计BNCT在水影中的剂量分布。一些常见的治疗癌症的方法，如brakhiterapi、手术、化疗和放疗，仍然有损害癌细胞周围健康组织的风险。BNCT是一种选择性设计的技术，通过在细胞水平上将高负载LET颗粒靶向肿瘤。事实证明，BNCT是一种在不损害正常组织的情况下杀死癌症的有效方法。利用PHITS程序计算了30 cm × 30 cm × 30 cm水幻影中回旋加速器剂量所使用的中子源。模拟结果表明，含硼水的辐射剂量比无硼水的辐射剂量高。
{"title":"Distribution of Water Phantom BNCT Cyclotron based Using PHITS","authors":"S. Maimanah, S. Susilo, Y. Sardjono","doi":"10.24246/ijpna.v4i1.1-7","DOIUrl":"https://doi.org/10.24246/ijpna.v4i1.1-7","url":null,"abstract":"This research purpose is to estimate the dose distribution of BNCT in water phantom. Some common methods in the treatment of cancer such as brakhiterapi, surgery, chemotherapy, and radiotherapy still have the risk of damaging healthy tissue around cancer cells. BNCT is a selectively-designed technique by targeting high-loaded LET particles to tumors at the cellular level. BNCT proves to be a powerful method of killing cancer without damaging normal tissue. The source of the neutron used from the cyclotron dose in water phantom with the size of 30 cm x 30 cm x 30 cm was calculated using PHITS program. The result from the simulation is that boron water panthom has a dosimetri higher than phantom water without boron.","PeriodicalId":383123,"journal":{"name":"Indonesian Journal of Physics and Nuclear Applications","volume":"15 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2019-08-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"124070365","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 : 2019-08-14DOI: 10.24246/ijpna.v4i1.27-32
Ramadhan Valiant Gill S Balle
Boron neutron capture therapy (BNCT) is an effective radiotherapy modality to kill cancer. BNCT can selectively kill cancer cells without damaging the healthy tissue around it by using alpha particle and lithium ion from the reaction of 10B(n,α)7Li. These particles have a track of more or less 5 to 9 μm which is the same as the cell diameter. In order to support the development of BNCT in Indonesia an in vivo simulation is performed in a simple mouse geometry containing a 4T1 breast cancer characteristic treated with BNCT using PHITS program. The Neutron source that was used in this simulation was based on TRIGA Kartini Research Reactor. The boron compound concentration in the tumor was varied from 20 ppm up to 90 ppm, and then the total dose was calculated in the mice. Total dose that the tumor received was 0.0161, 0.0168, 0.0175, 0.0182, 0.0185, 0.0188, 0.019, and 0.0191 Gy-Eq/s, respectively and the irradiation time to reach 50 Gy was 51, 50, 48, 46, 45, 45, 44, 44, 40 minutes respectively. This shows that the higher the concentration of boron compound in the tumor the higher the dose that mice received and irradiation time was decreased with the increase of the boron compound concentration.
{"title":"In Vivo Total Dose Analysis in Mice for BNCT Trial TRIGA Kartini Research Reactor Based Using PHITS","authors":"Ramadhan Valiant Gill S Balle","doi":"10.24246/ijpna.v4i1.27-32","DOIUrl":"https://doi.org/10.24246/ijpna.v4i1.27-32","url":null,"abstract":"Boron neutron capture therapy (BNCT) is an effective radiotherapy modality to kill cancer. BNCT can selectively kill cancer cells without damaging the healthy tissue around it by using alpha particle and lithium ion from the reaction of 10B(n,α)7Li. These particles have a track of more or less 5 to 9 μm which is the same as the cell diameter. In order to support the development of BNCT in Indonesia an in vivo simulation is performed in a simple mouse geometry containing a 4T1 breast cancer characteristic treated with BNCT using PHITS program. The Neutron source that was used in this simulation was based on TRIGA Kartini Research Reactor. The boron compound concentration in the tumor was varied from 20 ppm up to 90 ppm, and then the total dose was calculated in the mice. Total dose that the tumor received was 0.0161, 0.0168, 0.0175, 0.0182, 0.0185, 0.0188, 0.019, and 0.0191 Gy-Eq/s, respectively and the irradiation time to reach 50 Gy was 51, 50, 48, 46, 45, 45, 44, 44, 40 minutes respectively. This shows that the higher the concentration of boron compound in the tumor the higher the dose that mice received and irradiation time was decreased with the increase of the boron compound concentration.","PeriodicalId":383123,"journal":{"name":"Indonesian Journal of Physics and Nuclear Applications","volume":"0 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2019-08-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"129016566","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 : 2019-08-14DOI: 10.24246/ijpna.v4i1.22-26
O. D. Rahayuningsih, S. Susilo, Y. Sardjono
Cancer is the second leading cause of death globally and was responsible for 8,8 million deaths in 2015. Approximately 70% of deaths from cancer occur in low- and middle-income countries. The war on cancer has been fought with three tools – surgery (cut), radiation therapy (burn) including radiotherapy and bracytherapy, and also chemotherapy (poison). Cancer therapy has increased life expectancy of patients but each treatment modality has its own effects, complications and toxicity. Moreover we have found a new effective method to fight cancer, that is, Boron Neutron Capture Therapy (BNCT). Boron Neutron Capture Therapy (BNCT) has for many decades been advocated as an innovative form of radiotherapy that, in principle, has the potential to be the ideal form of treatment for many types of cancers. This research’s aim is the characterising neutron of BNCT water phantom based on 30 MeV cyclotron using PHITS computational code. The result from the simulation is that thickness of the water phantom, related to flux neutron.
{"title":"Neutron Chareacterization of BNCT Water Phantom Based on 30 MeV Cyclotron Using PHITS Computational Code","authors":"O. D. Rahayuningsih, S. Susilo, Y. Sardjono","doi":"10.24246/ijpna.v4i1.22-26","DOIUrl":"https://doi.org/10.24246/ijpna.v4i1.22-26","url":null,"abstract":"Cancer is the second leading cause of death globally and was responsible for 8,8 million deaths in 2015. Approximately 70% of deaths from cancer occur in low- and middle-income countries. The war on cancer has been fought with three tools – surgery (cut), radiation therapy (burn) including radiotherapy and bracytherapy, and also chemotherapy (poison). Cancer therapy has increased life expectancy of patients but each treatment modality has its own effects, complications and toxicity. Moreover we have found a new effective method to fight cancer, that is, Boron Neutron Capture Therapy (BNCT). Boron Neutron Capture Therapy (BNCT) has for many decades been advocated as an innovative form of radiotherapy that, in principle, has the potential to be the ideal form of treatment for many types of cancers. This research’s aim is the characterising neutron of BNCT water phantom based on 30 MeV cyclotron using PHITS computational code. The result from the simulation is that thickness of the water phantom, related to flux neutron.","PeriodicalId":383123,"journal":{"name":"Indonesian Journal of Physics and Nuclear Applications","volume":"81 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2019-08-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"130854816","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 : 2019-08-14DOI: 10.24246/ijpna.v4i1.8-11
rawi pramusinta, Rosilatul Zailani, Y. Sardjono
The purpose of this study is to know the concentration of boron and irradiation times which optimizes the treatment of breast cancer using the BNCT method. This research was conducted by using MCNPX simulation which outputs are flux neutron, neutron scattering dose and gamma dose. The neutron source used is the BSA D-D Neutron generator model. The independent variable of this research is the boron concentration injected into the cancer. The dependent variable is the total dose rate and irradiation time which determines the effectiveness of BNCT therapy. The controlled variables are the output of the neutron flux, dose and gamma neutron scattering dose. The results showed that in the range of 70-150 µg/g, the dose rate received by cancer increases with increasing the concentration of boron-10. If the dose rate is increased, the irradiation time interval will be faster. The Boron dose of 70 μg/g and the dose rate of irradiation 0.00293603 Gy/sec needs an irradiation time of 409.43 minutes; the boron dose of 90 µg/g and the dose rate of irradiation 0.00241049 Gy/sec needs an irradiation time of 345.71 minutes; the boron dose of 110 µg/g and the dose rate of irradiation 0.00271236 Gy/sec needs an irradiation time of 307.24 minutes; the boron dose of 130 µg/g and the dose rate of irradiation 0.00303389 Gy/sec needs an irradiation time of 274.67 minutes; and the boron dose 150 µg/g and the dose rate of irradiation 0.00334565 Gy/sec needs an irradiation time of 249.08 minutes. The Optimum concentration of boron is 150 µg/g with irradiation time of 249.08 minutes.
{"title":"Dose Analysis in Boron Neutron-capture Cancer Therapy (BNCT) Neutron Generator Based for Breast Cancer","authors":"rawi pramusinta, Rosilatul Zailani, Y. Sardjono","doi":"10.24246/ijpna.v4i1.8-11","DOIUrl":"https://doi.org/10.24246/ijpna.v4i1.8-11","url":null,"abstract":"The purpose of this study is to know the concentration of boron and irradiation times which optimizes the treatment of breast cancer using the BNCT method. This research was conducted by using MCNPX simulation which outputs are flux neutron, neutron scattering dose and gamma dose. The neutron source used is the BSA D-D Neutron generator model. The independent variable of this research is the boron concentration injected into the cancer. The dependent variable is the total dose rate and irradiation time which determines the effectiveness of BNCT therapy. The controlled variables are the output of the neutron flux, dose and gamma neutron scattering dose. The results showed that in the range of 70-150 µg/g, the dose rate received by cancer increases with increasing the concentration of boron-10. If the dose rate is increased, the irradiation time interval will be faster. The Boron dose of 70 μg/g and the dose rate of irradiation 0.00293603 Gy/sec needs an irradiation time of 409.43 minutes; the boron dose of 90 µg/g and the dose rate of irradiation 0.00241049 Gy/sec needs an irradiation time of 345.71 minutes; the boron dose of 110 µg/g and the dose rate of irradiation 0.00271236 Gy/sec needs an irradiation time of 307.24 minutes; the boron dose of 130 µg/g and the dose rate of irradiation 0.00303389 Gy/sec needs an irradiation time of 274.67 minutes; and the boron dose 150 µg/g and the dose rate of irradiation 0.00334565 Gy/sec needs an irradiation time of 249.08 minutes. The Optimum concentration of boron is 150 µg/g with irradiation time of 249.08 minutes.","PeriodicalId":383123,"journal":{"name":"Indonesian Journal of Physics and Nuclear Applications","volume":"72 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2019-08-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"126365896","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 : 2019-08-14DOI: 10.24246/IJPNA.V4I1.12-15
N. L. P. Suciptawati, M. Asih, Kartika Sari, I. Srinadi
The purpose of this study was to determine the factors that influence the infant mortality rate in Karangasem, Bali. The method used in this research is the Log Linier model. In the Log linear model analyze relationship pattern among group of categorical variables which include an association of two or more variables, either simultaneously or partially. A Patterned relationship between variables can be seen from the interaction between variables. Log linear analysis does not distinguish between explanatory variables and response variables. The population in this study was all babies born in Karangasem in 2015 that is as many as 7,895 babies with live birth status and as many as 7,835 babies and 60 infants died. As a sample, 100 babies were taken, of which 60 were live and 40 died. The results show that infant mortality is affected by infant weight, how old the mother during childbirth, and interaction between birth spacing and infant weight
{"title":"FACTORS AFFECTING INFANT MORTALITY RATE IN KARANGASEM, BALI","authors":"N. L. P. Suciptawati, M. Asih, Kartika Sari, I. Srinadi","doi":"10.24246/IJPNA.V4I1.12-15","DOIUrl":"https://doi.org/10.24246/IJPNA.V4I1.12-15","url":null,"abstract":"The purpose of this study was to determine the factors that influence the infant mortality rate in Karangasem, Bali. The method used in this research is the Log Linier model. In the Log linear model analyze relationship pattern among group of categorical variables which include an association of two or more variables, either simultaneously or partially. A Patterned relationship between variables can be seen from the interaction between variables. Log linear analysis does not distinguish between explanatory variables and response variables. The population in this study was all babies born in Karangasem in 2015 that is as many as 7,895 babies with live birth status and as many as 7,835 babies and 60 infants died. As a sample, 100 babies were taken, of which 60 were live and 40 died. The results show that infant mortality is affected by infant weight, how old the mother during childbirth, and interaction between birth spacing and infant weight \u0000 ","PeriodicalId":383123,"journal":{"name":"Indonesian Journal of Physics and Nuclear Applications","volume":"4 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2019-08-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"125735679","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 : 2019-08-14DOI: 10.24246/ijpna.v4i1.16-21
Vika Hutaria, S. Susilo, Y. Sardjono
Boron Neutron Capture Therapy (BNCT) is a therapy that utilizes the interaction of thermal neutrons with a boron-10 core that produces alpha particles and lithium nuclei. The result of this boron reaction has high linear energy transfer (LET). BNCT has an advantage over other radiation therapy in that it has a high selectivity level. This research was run using PHITS simulation to find out the value of neutron flux spread over a water phantom. The conclusion of the research is the distribution of neutron flux in the water phantom without boron is higher the the distribution of neutron flux in the water phantom containing boron
{"title":"Neutron Characterization of BNCT Water Phantom Based on Kartini Research Reactor Using PHITS","authors":"Vika Hutaria, S. Susilo, Y. Sardjono","doi":"10.24246/ijpna.v4i1.16-21","DOIUrl":"https://doi.org/10.24246/ijpna.v4i1.16-21","url":null,"abstract":"Boron Neutron Capture Therapy (BNCT) is a therapy that utilizes the interaction of thermal neutrons with a boron-10 core that produces alpha particles and lithium nuclei. The result of this boron reaction has high linear energy transfer (LET). BNCT has an advantage over other radiation therapy in that it has a high selectivity level. This research was run using PHITS simulation to find out the value of neutron flux spread over a water phantom. The conclusion of the research is the distribution of neutron flux in the water phantom without boron is higher the the distribution of neutron flux in the water phantom containing boron","PeriodicalId":383123,"journal":{"name":"Indonesian Journal of Physics and Nuclear Applications","volume":"20 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2019-08-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"133792608","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 : 2019-06-30DOI: 10.24246/IJPNA.V4I2.66-70
W. Widarto
Practical work at PSTA-BATAN to find paraffin design and the design of mobile devices with Monte Carlo N Particle (MCNP) software. The method used is to determine the paraffin design and calculate the volume of paraffin. The resulting intact writing that modeled with the MCNP. Shielding is required to absorb the leaking radiation until the 20 mSv / year Dose Limit Value for radiation workers is met. The material used is paraffin. Calculation is done by using MCNPX calculation facility with tariff of 10,42 μSv / hour. The paraffin design criteria are built on recommendations from Indonesian Journal of Physics and Nuclear Applications Volume 1, Number 1, February 2016. Some of the above-standard methods are overcome with the protection aspects of distance and radiation time. Paraffin used is made of hydrocarbons suitable for strengthening shielding structures and for absorbing gamma radiation.
{"title":"DESIGN AND MANUFACTURING DEVICE MOBILITY LOAD MOTION SHIELDING PARAFFIN RADIATION PROTECTION SYSTEM FACILITY TEST IN VITRO IN VIVO","authors":"W. Widarto","doi":"10.24246/IJPNA.V4I2.66-70","DOIUrl":"https://doi.org/10.24246/IJPNA.V4I2.66-70","url":null,"abstract":"Practical work at PSTA-BATAN to find paraffin design and the design of mobile devices with Monte Carlo N Particle (MCNP) software. The method used is to determine the paraffin design and calculate the volume of paraffin. The resulting intact writing that modeled with the MCNP. Shielding is required to absorb the leaking radiation until the 20 mSv / year Dose Limit Value for radiation workers is met. The material used is paraffin. Calculation is done by using MCNPX calculation facility with tariff of 10,42 μSv / hour. The paraffin design criteria are built on recommendations from Indonesian Journal of Physics and Nuclear Applications Volume 1, Number 1, February 2016. Some of the above-standard methods are overcome with the protection aspects of distance and radiation time. Paraffin used is made of hydrocarbons suitable for strengthening shielding structures and for absorbing gamma radiation. \u0000 ","PeriodicalId":383123,"journal":{"name":"Indonesian Journal of Physics and Nuclear Applications","volume":"54 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2019-06-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"117056234","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 : 2019-06-30DOI: 10.24246/IJPNA.V4I2.45-57
S. G. Pinasti
Measurement of radionuclides biodistribution in post-radioembolization 90Y SIRT is a part of treatment evaluation, in which the assessment of biodistribution is used to evaluate the possible extrahepatic presence and the absorbed dose estimation for the tumor cells, healthy liver cells, and critical organs. As the dose-response analysis is performed based on this evaluation, the biodistribution measurement coming from post-imaging modality has a crucial role in achieving these goals. The two devices, Single Photon Emission Tomography (SPECT) and Positron Emission Tomography are discussed in some aspects, including the quality of quantitative images, performance characteristics, and absorbed dose considerations.
{"title":"MEASUREMENT OF YTTRIUM-90 BIODISTRIBUTION IN SELECTIVE INTERNAL RADIATION THERAPY (SIRT)","authors":"S. G. Pinasti","doi":"10.24246/IJPNA.V4I2.45-57","DOIUrl":"https://doi.org/10.24246/IJPNA.V4I2.45-57","url":null,"abstract":"Measurement of radionuclides biodistribution in post-radioembolization 90Y SIRT is a part of treatment evaluation, in which the assessment of biodistribution is used to evaluate the possible extrahepatic presence and the absorbed dose estimation for the tumor cells, healthy liver cells, and critical organs. As the dose-response analysis is performed based on this evaluation, the biodistribution measurement coming from post-imaging modality has a crucial role in achieving these goals. The two devices, Single Photon Emission Tomography (SPECT) and Positron Emission Tomography are discussed in some aspects, including the quality of quantitative images, performance characteristics, and absorbed dose considerations.","PeriodicalId":383123,"journal":{"name":"Indonesian Journal of Physics and Nuclear Applications","volume":"21 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2019-06-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"122626320","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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