Indonesian Journal of Physics and Nuclear Applications
Indonesian Journal of Physics and Nuclear Applications is an international research journal, which publishes top level work from all areas of physics and nuclear applications including health, industry, energy, agriculture, etc. It is inisiated by results on research and development of Indonesian Boron Neutron Capture Cancer Therapy (BNCT) Consortium. Researchers and scientists are encouraged to contribute article based on recent research. It aims to preservation of nuclear knowledge; provide a learned reference in the field; and establish channel of communication among academic and research expert, policy makers and executive in industry, commerce and investment institution.
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80 Documents
<![CDATA[DESIGN AND MANUFACTURING DEVICE MOBILITY LOAD MOTION SHIELDING PARAFFIN RADIATION PROTECTION SYSTEM FACILITY TEST IN VITRO IN VIVO ]]>
<![CDATA[Widarto Widarto]]>
<![CDATA[ Indonesian Journal of Physics and Nuclear Applications Vol 4 No 2 (2019) ]]>
Publisher : <![CDATA[Fakultas Sains dan Matematika Universitas Kristen Satya Wacana ]]>
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DOI: 10.24246/ijpna.v4i2.66-70
<![CDATA[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.]]>
<![CDATA[COMMISSIONING TESTING FOR IN VITRO IN VIVO FACILITY AT RADIAL PIERCING BEAM-PORT OF THE KARTINI RESEARCH REACTOR FOR BORON NEUTRON CAPTURE CANCER THERAPY ]]>
<![CDATA[Widarto Widarto]]>
<![CDATA[ Indonesian Journal of Physics and Nuclear Applications Vol 4 No 2 (2019) ]]>
Publisher : <![CDATA[Fakultas Sains dan Matematika Universitas Kristen Satya Wacana ]]>
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<![CDATA[The purpose of the commissioning for in vitro in vivo test facility is to verify that the the facility has fulfilled the safety standards requirements, especially those related to radiation exposure. The standard requirement for environmental radiation exposure by IAEA is 20 mSv/hour. Otherwise results of the premilinary commissioning testing at the distance of 3 meters from in vitro in vivo test facility at radial piercing beam-port for 100 kW power level of the Kartini research reactor is for radiation exposure being around 9 mSv/hour. This means that the radiation exposure is less than the IAEA safety standard requirement of 20 mSv/hour. This is also less than the requirement of The Indonesian Regulatory Body limitation which is restricted to 15 mSv/hour. It can be concluded that when the reactor is operated at 100 kW power level for utilization by experiments in vitro/in vivo test, the facility is safe. However in order to be more safe at the restricted area, implementation of total quality management system should be completed with standard operating procedure (SOP) conducted with distance, time and shielding of radiation exposure for radiation safety protection system in utilization of the in vitro in vivo test facilities. When the SOP of the utilization of the in vitro in vivo test facility is implemented, the procedure is safer.]]>
<![CDATA[In Vitro and In Vivo Test of Boron Delivery Agent for BNCT ]]>
<![CDATA[Sista Dyah Wijaya]]>;
<![CDATA[Bagaswoto Poedjomartono]]>;
<![CDATA[Yohannes Sardjono]]>
<![CDATA[ Indonesian Journal of Physics and Nuclear Applications Vol 4 No 2 (2019) ]]>
Publisher : <![CDATA[Fakultas Sains dan Matematika Universitas Kristen Satya Wacana ]]>
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DOI: 10.24246/ijpna.v4i2.39-44
<![CDATA[BNCT is an alternate therapy for treating cancer. The principle of BNCT involves a neutron boron uptake and a fission reaction that produce alpha particles and Li ions with a high level of linear energy transfer in the tissue. It is effective in killing tumor cells. To administer boron in the tumor cells, a boron delivery agent is needed. Thus far, there are a variety of boron delivery agents that have been developed. To date, just two main boron-based drugs, BPA and BSH, have been used for clinical studies. Many other boron delivery agents have been evaluated in vivo and in vitro but have not been evaluated clinically. Therefore, the other boron delivery agents have not been used in BNCT clinical studies.]]>
<![CDATA[Boron Analysis and Imaging in BNCT ]]>
<![CDATA[Agus Permana Putra Sujana]]>
<![CDATA[ Indonesian Journal of Physics and Nuclear Applications Vol 5 No 2 (2020) ]]>
Publisher : <![CDATA[Fakultas Sains dan Matematika Universitas Kristen Satya Wacana ]]>
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DOI: 10.24246/ijpna.v5i2.38-60
<![CDATA[Boron Neutron Capture Therapy (BNCT) is a targeted therapy for cancer. BNCT uses boron 10 as media to do targeted therapy, eliminating cancer cell without damaging the surrounding healthy cell. BNCT require support from body imaging to acquire information about the cancer inside patient’s body while the analysis instrumen is use to analyze any parameter relevant to the medication, mainly chemical component of the delivery agents on the therapy and development. Journal divided into 2 , which is imaging and analysis. The imaging also divided into 2 which is imaging that use radioactivity and imaging that doesn’t use radioactivity. Boron analysis group uses analytical instrumentation and methods to gain information about boron outside the bodies ( in sample cell and delivery agents). Body imaging concerned with detecting and gaining information inside the biological object (patient or experiment subject). Information may consist of data about cancer distribution, patient organt condition and boron concentration within biological object.]]>
<![CDATA[The Microdosimetry Analysis of a BNCT Treatment for Liver Cancer Based on PHITS Code Simulation ]]>
<![CDATA[Hasna Atqona Aziizah]]>
<![CDATA[ Indonesian Journal of Physics and Nuclear Applications Vol 5 No 2 (2020) ]]>
Publisher : <![CDATA[Fakultas Sains dan Matematika Universitas Kristen Satya Wacana ]]>
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DOI: 10.24246/ijpna.v5i2.65-69
<![CDATA[Microdosimetry Analysis of a BNCT Treatment for Liver Cancer Based on PHITS Code Simulation. Cancer is a disease characterized by the growth and spread of abnormal cells that are not controlled. Liver cancer is in second position (788,000 deaths) as the cause of death after lung cancer. In resolving this chalenge, the BNCT method can be a solution. Boron Neutron Capture Therapy (BNCT) is a therapeutic technique based on irradiation from neutrons to boron-borne cancer cells (for liver cancer using 10boronophenylalanine (10BPA)) by utilizing neutron capture interactions with Boron-10. This study aims to analyzed microdosimetry of a BNCT treatment for liver cancer in different concentration of boron using PHITS code.]]>
<![CDATA[The Dose Evaluation Of In Vitro and In vivo Test In Kartini Research Reactor Facility Using PHITS Code ]]>
<![CDATA[Helga Dea Puspita]]>
<![CDATA[ Indonesian Journal of Physics and Nuclear Applications Vol 5 No 1 (2020) ]]>
Publisher : <![CDATA[Fakultas Sains dan Matematika Universitas Kristen Satya Wacana ]]>
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DOI: 10.24246/ijpna.v5i1.23-26
<![CDATA[Dose Evaluation of In Vitro and In Vivo Test In Kartini Reasearch Reactor BNCT Facility Using PHITS Code. this research is about dose analysis for in vitro and in vivo test by using PHITS program. The source of the neutron comes from a reactor that has been modified by previous researchers. In this research used mouse model. Modeling is done by modeling a mouse into a simple cylindrical geometry with a tumor modeled with the sphere geometry inside the cylinder]]>
<![CDATA[Beams Characteristic in Water Phantom Irradiation by Epithermal Neutron Beam from Double Layer Beam Shaping Assembly ]]>
<![CDATA[Bilalodin Bilalodin]]>;
<![CDATA[Kusminarto Kusminarto]]>;
<![CDATA[Arief Hermanto]]>;
<![CDATA[Yohannes Sardjono]]>
<![CDATA[ Indonesian Journal of Physics and Nuclear Applications Vol 5 No 1 (2020) ]]>
Publisher : <![CDATA[Fakultas Sains dan Matematika Universitas Kristen Satya Wacana ]]>
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DOI: 10.24246/ijpna.v5i1.18-22
<![CDATA[A Double Layer Beam Shaping Assembly (DLBSA) is designed to produce epithermal neutrons for BNCT purposes. The MCNPX program is utilized as the software to design the DLBSA and phantom. Distribution of epithermal neutron and gamma flux in the DLBSA and phantom and absorbed dose in phantom are computed using the Particle and Heavy Ion Transport System (PHITS) program. Testing results of epithermal neutron beams irradiation on water phantom shows that epithermal neutrons are thermalized and penetrate the phantom up to 12 cm in depth. Maximum value of absorbed dose is 2 x 10-3 Gy at a depth of 2 cm in phantom.]]>
<![CDATA[ROCKWELL HARDNESS TESTING ON PURE NICKEL KOLIMATOR FOR BNCT APPLICATION ]]>
<![CDATA[erasmus prakas ita]]>
<![CDATA[ Indonesian Journal of Physics and Nuclear Applications Vol 5 No 1 (2020) ]]>
Publisher : <![CDATA[Fakultas Sains dan Matematika Universitas Kristen Satya Wacana ]]>
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DOI: 10.24246/ijpna.v5i1.9-17
<![CDATA[In this study, Rockwell is used in material hardness examination. It caused by those characteristics. Those are, fast, away from human error, from this examination it can be known and compared the characteristics of nickel porosity before sentrifugal casting and after sentrifugal casting through hardness testing. To discover the element of nickel 99% porosity in Boron Neutron Capture Therapy (BNCT). the component used in BNCT in cylindrical shape and created in Sentrifugal casting method. The method which is used in this this project is hardness testing.]]>
<![CDATA[NDT TESTING USING NEUTRON RADIOGRAPHY METHOD ON PURE NICKEL COLLIMATOR FOR BNCT APPLICATION ]]>
<![CDATA[Ricky Fajar Adiputra]]>
<![CDATA[ Indonesian Journal of Physics and Nuclear Applications Vol 5 No 1 (2020) ]]>
Publisher : <![CDATA[Fakultas Sains dan Matematika Universitas Kristen Satya Wacana ]]>
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DOI: 10.24246/ijpna.v5i1.1-8
<![CDATA[Boron neutron capture therapy (BNCT) is a targeted radiotherapy technique developed to treat patients with selected malignant tumors without any side effect. Colimator is one of important component used in BNCT. In this research collimator made by centrifugal casting processes which can cause any defect. Purpose of the research is to detect any defect in collimator made by 99% pure nickel with Neutron Radiography and processing with MNCP5 for imaging the defect. The expected result of this research is displayed an image of defect caused by centrifugal casting in collimator.]]>
<![CDATA[The STATE-OF-THE-ART ON RADIOACTIVE SLUDGE FROM SPENT FUEL REPROCESSING ]]>
<![CDATA[Agung Prastowo]]>
<![CDATA[ Indonesian Journal of Physics and Nuclear Applications Vol 5 No 1 (2020) ]]>
Publisher : <![CDATA[Fakultas Sains dan Matematika Universitas Kristen Satya Wacana ]]>
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DOI: 10.24246/ijpna.v5i1.27-30
<![CDATA[Radioactive sludge has been produced from the co-precipitation process of spent nuclear fuel reprocessing, which is derivative waste that requires special attention in waste management methods. This study examines the development of research applied by countries with the civilian nuclear program. Proper methods regarding radioactive sludge conditioning are used as a reference for waste management determining radioactive sludge which is one of the main focuses in waste recovery and conditioning (RCD) projects at Orano la Hague, France. Radioactive sludge has been conditioned using bitumen, where the French nuclear safety authority does not permit it because of the radiolysis issue in the waste storage package. Therefore, new methods for bitumen replacement and radioactive sludge storage packages are needed to replace it by the provisions of the French Nuclear Safety Agency. A systematic literature review method is used to provide an analysis of the methods for radioactive sludge waste conditioning that have been synthesized from several related studies to provide an overview of the current issues. The HPing and plasma filtering methods were developed at Sellafield and Hanford with the advantage of reducing the significant volume of waste and chemical composition.]]>
