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INDONESIA
Indonesian Journal of Physics and Nuclear Applications
ISSN : 2549046X     EISSN : -     DOI : -
Core Subject : Science, Social,
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 80 Documents
The Optimization of Collimator Material and In Vivo Testing Dosimetry of Boron Neutron Capture Therapy (BNCT) on Radial Piercing Beam Port Kartini Nuclear Reactor by Monte Carlo N-Particle Extended (MCNPX) Simulation Method Yohannes Sardjono; Kusminarto Kusminarto; Ikna Urwatul Wusko
Indonesian Journal of Physics and Nuclear Applications Vol 3 No 1 (2018)
Publisher : Fakultas Sains dan Matematika Universitas Kristen Satya Wacana

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (652.956 KB) | DOI: 10.24246/ijpna.v3i1.29-35

Abstract

Boron Neutron Capture Therapy (BNCT) on radial piercing beam port Kartini nuclear reactor by MCNPX simulation method has been done in the National Nuclear Energy Agency Yogyakarta. BNCT is a type of therapy alternative that uses nuclear reaction 10B (n, α) 7Li to produce 2.79 MeV total kinetic energy. To be eligible IAEA conducted a study of design improvements and variations on some parameters to optimum condition which are Ni-nat thickness of 1.75 cm as collimator wall, Al2S3 as thick as 29 cm as moderator, Al2O3 0.5 cm thick as filter, Pb and Bi thickness of 4 cm as the end of the gamma shield collimators and Bi thickness of 1.5 cm as the base gamma shield collimators. The total dose was accepted in the tumor tissue 900 × 10-4 Gy/s. Radiation dose on the tumor tissue is 50±3 Gy with time irradiation of 9 minutes and 10 seconds. That dose was given into skin tissue and healthy liver tissue consecutively (6.00±0.05) × 10-2 Gy and (10.00±0.05) × 10-2 Gy. It shows the dose received by healthy tissue is still within safe limits.
Assesment of Boron Neutron Capture Therapy (BNCT): Compact Neutron Generators Nur Setyo Wahyuni; Yohannes Sardjono
Indonesian Journal of Physics and Nuclear Applications Vol 3 No 2 (2018)
Publisher : Fakultas Sains dan Matematika Universitas Kristen Satya Wacana

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (230.929 KB) | DOI: 10.24246/ijpna.v3i2.36-42

Abstract

Boron Neutron Capture Therapy (BNCT) is an effective and promising treatment of tumour types which are resistant to conventional therapies. The characteristics of boron neutron capture therapy (BNCT) for cancer treatment demand, in addition to sufficient fluxes of epithermal neutrons, proper conditions of the neutron sources—compact layout, flexible operation, compatibility with hospital setting, etc. The lack of proper neutron sources that can be integrable to the infrastructure of hospital or clinical facilities is a major problem. Compact neutron generators (CNGs), which are the most compact and least expensive, were a potential, alternative, solution to existing BNCT treatment facilities based on nuclear reactors. This paper will provide information about the latest CNGs technology development that has contributed to the Boron Neutron Capture Therapy (BNCT) technology improvement.
Review on Some Computational Aspects of Boron Neutron Capture Therapy Liem Peng Hong
Indonesian Journal of Physics and Nuclear Applications Vol 3 No 2 (2018)
Publisher : Fakultas Sains dan Matematika Universitas Kristen Satya Wacana

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (844.742 KB) | DOI: 10.24246/ijpna.v3i2.56-63

Abstract

This paper reviews some computational aspects of Boron Neutron Capture Therapy (BNCT) with the emphasis on the BNCT treatment planning system. An example of a computational dosimetry system developed in Japan is discussed, particularly, the need of such system for BNCT which uses epithermal neutron beams for non-craniotomy brain tumors as well as head-&-neck cancers. An example of BNCT dose calculation method is also presented.
Distribution of Water Phantom BNCT Kartini Research Reactor Based Using PHITS Nunung Gupita Ratnasari; Susilo Susilo; Yohannes Sardjono
Indonesian Journal of Physics and Nuclear Applications Vol 3 No 2 (2018)
Publisher : Fakultas Sains dan Matematika Universitas Kristen Satya Wacana

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (439.245 KB) | DOI: 10.24246/ijpna.v3i2.43-48

Abstract

The purpose of this research was to calculate the radiation dose on BNCT. Boron Neutron Capture Therapy (BNCT) is a cancer therapy which utilizes thermal neutron-capture reactions by boron-10 isotopes that produce alpha particles and lithium nuclei. The advantage of BNCT is that radiation effects can be limited to tumor cells. The dose of radiation on BNCT depends heavily on the distribution of boron and the neutron free region. The calculation method involves alpha and lithium particles of reactions having high Linear Energy Transfer (LET). By replacing the target of using water phantom that contains heavy water and covered by acrylic glass measuring 30 cm x 30 cm x 30 cm, the dose is calculated using PHITS-based applications. By comparing the simulation results between boron and phantom water or phantom without boron then the conclusion is the absorbed dose of phantom water containing boron is larger than phantom water without boron.
RADIOACTIVE WASTE TREATMENT OF OIL AND GAS INDUSTRY Alifia Darmayanti; Yohannes Sardjono; Sri Yuniarti
Indonesian Journal of Physics and Nuclear Applications Vol 3 No 2 (2018)
Publisher : Fakultas Sains dan Matematika Universitas Kristen Satya Wacana

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (293.155 KB) | DOI: 10.24246/ijpna.v3i2.49-55

Abstract

The increase of energy needs leads to the increase of oil and gas industry in Indonesia. Along with this, a good understanding about the application of radioactive materials, the treatment of radioactive waste and its disposal is needed. It is important because nowadays the radiation-based technologies are widely used by oil and gas industry, and a good understanding of the mentioned points will enable us to provide better and improved treatment as we strive to achieve clean technology. The uses of radioactive materials in the oil and gas industry are in exploration, producing, refineries, inspection of facilities, laboratories, and industrial security. The treatment of radioactive waste from oil and gas industry are divided into aqueous waste treatment, organic liquid waste treatment, and solid waste treatment.
ANALYSIS OF CS-137 TO CS-134 ACTIVITY RATIO FOR FAILED FUEL EXPOSURE ESTIMATION Ren-Tai Chiang
Indonesian Journal of Physics and Nuclear Applications Vol 3 No 3 (2018)
Publisher : Fakultas Sains dan Matematika Universitas Kristen Satya Wacana

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (197.245 KB) | DOI: 10.24246/ijpna.v3i3.76-82

Abstract

The Cs-134 to Cs-137 activity ratio of the Cs-134 and Cs-137 fission products released from failed fuel rods into primary coolant is very useful to identify the exposure along with the fuel batch of the failed fuel. The calculated and measured Cs-137 to Cs-134 radioactivity ratios of failed BWR and PWR fuels are compared and analyzed for better understanding of their relationship. Moreover, the impacts of power uprate and fuel reload outage on calculated Cs-137 to Cs-134 activity ratios are studied and the physics behind the impacts are provided.
BRAIN TUMOR DETECTION USING BACKPROPAGATION NEURAL NETWORKS Iklas Sanubary
Indonesian Journal of Physics and Nuclear Applications Vol 3 No 3 (2018)
Publisher : Fakultas Sains dan Matematika Universitas Kristen Satya Wacana

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (361.139 KB) | DOI: 10.24246/ijpna.v3i3.83-88

Abstract

A study of brain tumor detection has been done by making use of backpropagation neural networks with Gray Level Co-Occurrence Matrix (GLCM) feature extraction. CT-Scan images of the brain consist of 12 normal and 13 abnormal (tumor) brain images are analyzed. The preprocessing stage begins with cropping the image to a 256 x 256 pixels picture, then converting the colored images into grayscale images, and equalizing the histogram to improve the quality of the images. GLCM is used to calculate statistical features determined by 5 parameters i.e., contrast, correlation, energy and homogeneity for each direction. In these backpropagation neural networks, the [12 2 1] architecture is used. The correlation coefficient between the target and the output for the training data is 0.999, while the correlation coefficient for the testing data is 0.959 with an accuracy of 70%. The results of this research indicate that backpropagation neural networks can be used for the detection of brain tumors.
COPULA MODELING IN ANALYSIS OF DEPENDENCY OF OIL PALM PRODUCTION AND RAINFALL Dadan Kusnandar; Naomi Nessyana Debataraja; Shantika Marthal
Indonesian Journal of Physics and Nuclear Applications Vol 3 No 3 (2018)
Publisher : Fakultas Sains dan Matematika Universitas Kristen Satya Wacana

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (667.838 KB) | DOI: 10.24246/ijpna.v3i3.89-94

Abstract

Copula is a method that examines the relationship pattern between variables. Copula is characterized as a nonparametric method with several benefits, i.e., it is independent of the assumption of the distribution, accommodates nonlinear relationship among variables, and is convenient in building joint distribution. This study investigates the relationship and prediction analysis using the copula approach. The method is applied to the monthly data of oil palm production and the amount of rainfall. The results show that the model of Frank Copula is the best model for rainfall and oil palm production relationship.
THE DOSE ANALYSIS OF BORON NEUTRON CAPTURE THERAPY (BNCT) TO THE BRAIN CANCER (GLIOBLASTOMA MULTIFORM) USING MCNPX-CODE WITH NEUTRON SOURCE FROM COLLIMATED THERMAL COLUMN KARTINI RESEARCH NUCLEAR Kholidah Hasyim; Yohannes Sardjono; Yosaphat Sumardi
Indonesian Journal of Physics and Nuclear Applications Vol 3 No 3 (2018)
Publisher : Fakultas Sains dan Matematika Universitas Kristen Satya Wacana

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (683.433 KB) | DOI: 10.24246/ijpna.v3i3.95-101

Abstract

This research was aimed at discovering the optimum concentration of Boron-10 in concentrations range 20 µgram/gram until 35 µgram/gram with Boron Neutron Capture Therapy (BNCT) methods and the shortest time irradiation for cancer therapy. The research about dose analysis of Boron Neutron Capture Therapy (BNCT) to the brain cancer (Glioblastoma Multiform) using MCNPX-Code with a neutron source from Collimated Thermal Column Kartini Research Nuclear has been conducted. This research was a simulation-based experiment using MCNPX, and the data was arranged on a graph using OriginPro 8. The modelling was performed with the brain that contains cancer tissue as a target and the reactor as a radiation source. The variations of Boron concentrations in this research was on 20, 25, 30 and 35 μg/gram tumours. The outputs of MCNP were neutron scattering dose, gamma ray dose and neutron flux from the reactor. Neutron flux was used to calculate the doses of alpha, proton and gamma rays produced by the interaction of tissue material and thermal neutrons. Based on the calculations, the optimum concentration of Boron-10 in tumour tissue was for a 30 µg/gram tumour with the radiation dose in skin at less than 3 Gy. The irradiation times required were 2.79 hours for concentration 20 μg/gram ; 2.78 hours for concentration 25 μg/gram ; 2.77 hours for concentration 30 μg/gram ; 2.8 hours for concentration 35 μg/gram.
ANIMATION OF BORON NEUTRON CAPTURE CANCER THERAPY Indra Maulana
Indonesian Journal of Physics and Nuclear Applications Vol 3 No 3 (2018)
Publisher : Fakultas Sains dan Matematika Universitas Kristen Satya Wacana

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (441.849 KB) | DOI: 10.24246/ijpna.v3i3.102-112

Abstract

One of the most common causes of death in the world is cancer. Scientists have been trying to find the best cure for cancer ever since it was discovered. There are some ways that are used to treat cancer patients. Lately, scientists have developed a new way in treating cancer, it’s called Boron Neutron Capture Therapy (BNCT). BNCT is a selective cancer therapy, it only selects the cancer cells to be treated and leaves the normal cell untouched. It may have no effect or only a little effect on normal cells. As new knowledge that needs to be known by all people, what is the best way to introduce BNCT? What is the best media to introduce BNCT? Is it enough to just read it in a newspaper or in a book? How about using advanced technology such as animation to introduce BNCT? The use of animation as a form of media to introduce something new is already being done in many fields. Can animation be used as a form of media to introduce BNCT too? Will it be effective? By this study, the author gives information about the effect of using animation as a tool to explain and understand BNCT more.