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Indonesian Journal of Physics and Nuclear Applications

ijpna
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Published by Universitas Kristen Satya Wacana

ISSN : 2549046X EISSN : - DOI : -

Core Subject : Science, Social,

Environmental Science Physics

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.

Arjuna Subject : -

Articles 5 Documents

Search results for , issue "Vol 2 No 3 (2017)" : 5 Documents clear

CREATIVE ENVIRONMENTAL ENERGY TECHNOLOGY ASSESSMENT HYDROELECTRIC POWER PLANT (CASE STUDY OF WONOGIRI RESERVOIR) Feby Hidayani; Yohanes Sardjono; Chafid Fandeli; Rukmini A.R
Indonesian Journal of Physics and Nuclear Applications Vol 2 No 3 (2017)
Publisher : Fakultas Sains dan Matematika Universitas Kristen Satya Wacana

Hydroelectric power plants in Indonesia are widely developed. This is because the water supply in Indonesia is quite abundant. Several large reservoirs in Indonesia, in addition to being used for water reservoirs, are used to produce electricity. Wonogiri is a region that is located in Central Java province, where most of the region is arid land that cannot be planted in the dry season. In the rainy season the abundance of water plants to die and the soil is such that in the dry season crops do not grow well. Plans for the construction of Gajah Mungkur started in 1964, and it is designed to be a multipurpose dam project that aim to control floods, supply water for irrigation and hydropower in the Solo River valley. The master development plan was formulated in 1972-1974 with the help of Overseas Technical Cooperation of Japan. The results of this study include the completion of flooding problems along the Solo River, the increase in agricultural output in Winton community with irrigation facilities and good infrastructure, availability of electricity for communities around the dam and improving the local economy as the development of inland fisheries and tourism sectors.

Double Layer Collimator for BNCT Neutron Source Based on 30 MeV Cyclotron Bilalodin Bilalodin; Kusminarto Kusminarto; Arief Hermanto; Yohannes Sardjono; Sunardi Sunardi
Indonesian Journal of Physics and Nuclear Applications Vol 2 No 3 (2017)
Publisher : Fakultas Sains dan Matematika Universitas Kristen Satya Wacana

A research of design of double layer collimator using 9Be(p,n) neutron source has been conducted. The research objective is to design a double layer collimator to obtain neutron sources that are compliant with the IAEA standards. The approach to the design of double layer collimator used the MCNPX code. From the research, it was found that the optimum dimensions of a beryllium target are 0.01 mm in length and 9.5 cm in radius. Collimator consists of a D2O and Al moderator, Pb and Ni as a reflector, and Cd and Fe as a thermal and fast neutron filter. The gamma filter used Bi and Pb. The quality neutron beams emitted from the double layer collimator is specified by five parameters: epithermal neutron flux 1 ×109 n/cm2s; fast neutron dose per epithermal neutron flux 5 ×1013 Gy cm2s; gamma dose per epithermal neutron flux 1×1013 Gy cm2s; ratio of the thermal neutron flux of epithermal neutron flux 0; and the ratio of epithermal neutron current to total epithermal neutron 0.54.

OPTIMIZATION OF COLLIMATOR NEUTRON DESIGN FOR BORON NEUTRON-CAPTURE CANCER THERAPY (BNCT) BASED CYCLOTRON 30 MeV Aniti Payudan; Aris Haryadi; Farzand Abdullatif
Indonesian Journal of Physics and Nuclear Applications Vol 2 No 3 (2017)
Publisher : Fakultas Sains dan Matematika Universitas Kristen Satya Wacana

This research in BNCT has a goal to design a collimator that can be used for cancer therapy. Simulations were carried out by MCNPX software. A collimator is designed by cyclotron 30 MeV as a neutron generator. Independent variables varied were material and thickness of each collimator’s component to get five of IAEA’s standard of the neutron beam. The result is two collimator designs that can pass all IAEA’s standard. Those designs are cyclotron collimator I and cyclotron collimator II. Collimator designs obtained are tube collimator consisting of a cylindrical target 7Be length of 1.4 cm and radius 1 cm, a lead wall with thickness 23 cm, cylindrical heavy water moderator (D2O) with radius 3 cm. Filter Cd-nat for cyclotron collimator I with a thickness of 1 mm and a radius 3 cm. Cyclotron collimator II uses 60Ni with a thickness of 5 cm as a filter. The radius aperture is 3 cm. These two collimator designs can be used for cancer treatment with BNCT. Dosimetry calculation and manufacture of prototypes are needed to test the application of this design.

THE EFFECT OF THICKNESS VARIATION OF BERYLLIUM TARGET TOWARD CHARACTERISTICS OF NEUTRON ENERGY SPECTRUM ON CYCLOTRONS HM-30 USING MCNP-X Sri Yuniarti; Aris Haryadi; R Farzand Abdullatif
Indonesian Journal of Physics and Nuclear Applications Vol 2 No 3 (2017)
Publisher : Fakultas Sains dan Matematika Universitas Kristen Satya Wacana

The research about the characterization of neutron energy spectrum as the effect of thickness variation of beryllium (Be) target on HM−30 cyclotron using Monte Carlo N−Particle eXtended (MCNP−X) has been conducted. This research aims to know the characteristics of neutron energy spectrum which are the result ofed by the reaction of Be(p,n) with HM−30 cyclotron as one of BNCT facilities. Modelling and simulation have been done by using MNCP−X software, then the data obtained is arranged on a graph by using Origin 8+. The result of the simulation shows that the characteristics of neutron energy spectrum of each thickness are in the range of fast neutron energy. The thicker the Beryllium target, the more diminishing the neutron energy will be.

DOSE ANALYZE OF BORON NEUTRON CAPTURE THERAPY (BNCT) AT SKIN CANCER MELANOMA USING MCNPX WITH NEUTRON SOURCE FROM THERMAL COLUMN OF KARTINI REACTOR Siti Rosidah; Yohannes Sardjono; Yosaphat Sumardi
Indonesian Journal of Physics and Nuclear Applications Vol 2 No 3 (2017)
Publisher : Fakultas Sains dan Matematika Universitas Kristen Satya Wacana

This research aims to determine the amount of radiation dose rate that can be accepted and the irradiation time that is required from Boron Neutron Capture Therapy (BNCT) cancer therapy to treat melanoma skin cancer. This research used the simulation program, MCNPX by defining the geometric dimensions of the tissue component, and describing the radiation source that were used. The outputs obtained from the MCNPX simulation were the neutron flux and the neutron scattering dose that came out from the collimator. The value of neutron flux was used to calculate the dose which comes from the interaction between the neutron and the material in the cancer tissue. Based on the results of the research, the dose rate to treat cancer tissue for boron is 10 μg/g of tumor, which translates to about 0.019241 Gy/second and requires 25.98 minutes of irradiation time, 15 μg/g of tumor translates to 0.021854 Gy/second and requires 2.,87 minutes, 20 μg/g of tumor translates to 0.022902 Gy/second and requires 21,83 minutes, 25 μg/g of tumor translates to 0.0271275 Gy/second and requires 18.43 minutes, 30 μg/g of tumor translates to 0.0297658 Gy/second and requires 16.79 minutes, and 35 μg/g of tumor translates to 0.0343472 Gy/second and requires 14.55 minutes . The irradiation time needed for cancer tissue is shorter when boron concentration greater at the cancerous tissue.

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