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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 6 Documents

Search results for , issue "Vol 4 No 2 (2019)" : 6 Documents clear

MEASUREMENT OF YTTRIUM-90 BIODISTRIBUTION IN SELECTIVE INTERNAL RADIATION THERAPY (SIRT) Sita Gandes Pinasti
Indonesian Journal of Physics and Nuclear Applications Vol 4 No 2 (2019)
Publisher : Fakultas Sains dan Matematika Universitas Kristen Satya Wacana

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.

COMPUTATIONAL FLUID DYNAMICS SIMULATION OF KARTINI REACTOR FUELED PLATE Tri Nugroho Hadi Susanto
Indonesian Journal of Physics and Nuclear Applications Vol 4 No 2 (2019)
Publisher : Fakultas Sains dan Matematika Universitas Kristen Satya Wacana

The purpose of this study is to determine the characteristics of the cooling system on the new design of the Kartini Reactor plate fuel based on numerical calculations (Computational Fluid Dynamics). The fuel plate model was simplified and made in 3D. The model dimensions are 17.3 mm x 68 mm x 900 mm. The space between the two plates called the narrow rectangular channels has a gap of 2 mm. On these simulations a heat flux of 10612,7 watt/m2 was used which was obtained from the MCNP calculation program. Simulations were conducted in a steady state condition and single-phase model laminar flow of an incompressible fluid through the gap between the two fuel plates. This simulation uses UDF (User Define Function) to approach heat flux behaviour that follows the neutron distribution in the reactor core. The simulation results show that the maximum temperature that occur at a flow rate of 0.01 m/s was 43.5 °C.

MONTE CARLO N PARTICLE EXTENDED (MCNPX) RADIATION SHIELD MODELLING ON BORON NEUTRON CAPTURE THERAPY FACILITY USING D-D NEUTRON GENERATOR 2.4 MeV Yohannes Sardjono
Indonesian Journal of Physics and Nuclear Applications Vol 4 No 2 (2019)
Publisher : Fakultas Sains dan Matematika Universitas Kristen Satya Wacana

Based Studies were carried out to analyze the internal dose of radiation for workers at Boron Neutron Capture Therapy (BNCT) facility base on Cyclotron 30 MeV with BSA and a room that was actually designed before. This internal dose analyzation included interaction between neutrons and air. The air contained N2 (72%), O2 (20%), Ar (0.93%), CO2, Neon, Kripton, Xenon, Helium and Methane. That internal dose to the worker should be below the dose limit for radiation workers which is an amount of 20 mSv/years. From the particles that are present in the air, only Nitrogen and Argon can change into radioactive element. Nitrogen-14 activated to Carbon-14, Nitrogen-15 activated to Nitrogen-16, and Argon-40 activated to Argon-41. Calculation using tally facility in Monte Carlo N Particle version Extended (MCNPX) program for calculated Neutron flux in the air 3.16x107 Neutron/cm2s. The room design in the cancer facility has a measurement of 200 cm in length, 200 cm in width, and 166.40 cm in height. Neutron flux can be used to calculate the reaction rate which is 80.1x10-2 reaction/cm3s for carbon-14 and 8.75x10-5 reaction/cm3s. The internal dose exposed to the radiation worker is 9.08E-9 µSv.

DESIGN AND MANUFACTURING DEVICE MOBILITY LOAD MOTION SHIELDING PARAFFIN RADIATION PROTECTION SYSTEM FACILITY TEST IN VITRO IN VIVO Widarto Widarto
Indonesian Journal of Physics and Nuclear Applications Vol 4 No 2 (2019)
Publisher : Fakultas Sains dan Matematika Universitas Kristen Satya Wacana

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.

COMMISSIONING TESTING FOR IN VITRO IN VIVO FACILITY AT RADIAL PIERCING BEAM-PORT OF THE KARTINI RESEARCH REACTOR FOR BORON NEUTRON CAPTURE CANCER THERAPY Widarto Widarto
Indonesian Journal of Physics and Nuclear Applications Vol 4 No 2 (2019)
Publisher : Fakultas Sains dan Matematika Universitas Kristen Satya Wacana

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (857.072 KB)

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.

In Vitro and In Vivo Test of Boron Delivery Agent for BNCT Sista Dyah Wijaya; Bagaswoto Poedjomartono; Yohannes Sardjono
Indonesian Journal of Physics and Nuclear Applications Vol 4 No 2 (2019)
Publisher : Fakultas Sains dan Matematika Universitas Kristen Satya Wacana

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.

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