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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.

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Articles 5 Documents

Search results for , issue "Vol 3 No 1 (2018)" : 5 Documents clear

Safety Features of Advanced and Economic Simplified Boiling Water Reactors Ren-Tai Chiang
Indonesian Journal of Physics and Nuclear Applications Vol 3 No 1 (2018)
Publisher : Fakultas Sains dan Matematika Universitas Kristen Satya Wacana

The Advanced Boiling Water Reactor (ABWR) and the Economic Simplified Boiling Water Reactor (ESBWR) are two kinds of contemporary, advanced, commercially available nuclear power reactors. Reactor internal pumps in an ABWR improve performance while eliminating the large recirculation pumps in earlier BWRs. The utilization of natural circulation and passive safety systems in the ESBWR design simplifies nuclear reactor system designs, reduces cost, and provides a reliable stability solution for inherently safe operation. The conceptually reliable stability solution for inherently safe ESBWR operation is developed by establishing a sufficiently high natural circulation flow line, which has a core flow margin at least 5% higher than the stability boundary flow at 100% rated power of a conventional BWR, and then by designing a high flow natural circulation system to achieve this high natural circulation flow line. The performance analyses for the ESBWR Emergency Core Cooling System (ECCS) show that: (1) the core remains covered with a large margin and there is no core heat up in the ESBWR for any break size, (2) the long-term containment pressure increases gradually with time, in the order of hours, and the peak pressure is below the design value with a large margin, and (3) the margins depend on the containment volumes and water inventories. These safety design features ensure inherently safe ESBWR operation. Enhanced safety features based on lessons learned from the Fukushima nuclear accident are added in ABWR’s and ESBWR’s safety designs. The major enhancements are the further prevention of station blackout and loss of ultimate heat sink.

Study on the Ability of PCMSR to Produce Valuable Isotopes as a By Product of Energy Generation Andang Widiharto
Indonesian Journal of Physics and Nuclear Applications Vol 3 No 1 (2018)
Publisher : Fakultas Sains dan Matematika Universitas Kristen Satya Wacana

PCMSR (Passive Compact Molten Salt Reactor) is a variant of MSR (Molten Salt Reactor) type reactors. The MSR is one type of the Advanced Nuclear Reactor types. PCMSR uses mixtures of fluoride salt if the liquid form is in a high temperature operation. The use of liquid salt fuel allows the application of on line fuel processing system. The on line fuel processing system allows extraction of several valuable fission product isotopes such as Mo-99, Cs-137, Sr-89 etc. The capability of MSR to produce several valuable isotopes has been studied. This study is based on a denaturized breeder MSR design with 920 MWth of thermal power and 500 MWe of electrical output power with the thermal efficiency of 55 %. The initial composition of fuel salt is 70 % of a mole of LiF, 24 % of a mole of 232ThF4, 6 % of a mole of UF4. The enrichment level of U is 20 % of a mole of U-235. The study is performed by a numerical calculation to solve a set of differential equations of fission product balance. This calculation calculates fission product generation due to fission reaction, precursor decay, and fission product annihilation due to decay, neutron absorption, and extraction. The calculation result shows that in quasi equilibrium conditions, the reactor can produce several valuable isotopes in substantially sufficient quantities, those are Sr-89 (0.3 kCi/MWth/day, Sr-90 (1,91 Ci/MWth/day), Mo-99 (1.7 kCi/MWth/day), I-131 (0.42 kCi/MWth/day), I-132 (0.782 kCi/MWth/day), I-133 (1.12 kCi/MWth/day), Xe-133 (11.8 Ci/MWth/day), Cs-134 (39.3 mCi/MWth/day), Cs-137 (2.32 Ci/MWth/day) and La-140 (1.05 kCi/MWth/day).

Detail Engineering Design of Compact Neutron Generator to Support BNCT Facility in Indonesia Widarto Widarto
Indonesian Journal of Physics and Nuclear Applications Vol 3 No 1 (2018)
Publisher : Fakultas Sains dan Matematika Universitas Kristen Satya Wacana

Boron Neutron Capture Therapy (BNCT) is a method of cancer therapy based on neutron radiation which has advantages over the other cancer therapy methods. It uses a stable isotope of 10B which will be an excited isotope of 11B when irradiated by thermal neutron. It immediately (in 10-12 s) breaks into α particle and a lithium recoil nucleus. The two secondary particles play important roles in killing cancer cells. They have a short range in tissue (5 µm and 9 µm respectively) which is less than the average dimension of a cell. This leads to the damage of cancer cell only but the normal cells remain safe. Thermal and epithermal neutrons play important roles in BNCT. From the beginning the neutron sources for BNCT are nuclear reactors which produce high intensity of thermal neutrons (En <0.5 eV), epithermal neutrons (0.5 eV< En < 10 keV) and fast neutrons (En > 10 keV). However, nuclear reactors are very expensive and too large to be used in hospitals. In addition, the operation of nuclear reactors is under restricted protocols related to safety and physical protection. A compact neutron generator is a good choice of neutron source for BNCT. The advantages of compact neutron generator are that the size is small and that the neutron yield is more than 109 ns-1 which satisfies the requirement recommended by IAEA. Additionally, the neutron energy is not so high that it requires a complicated neutron collimator, the operation is easy, and the public acceptance is higher than with nuclear reactors. Based on the requirements of epithermal neutron beam for BNCT facility, the detailed engineering design of compact neutron generator has been made.

Manufacture of Nickel Collimator for BNCT: Smelting of Nickel Using Electrical Arc Furnace and Centrifugal Casting Preparation Mujiyono Mujiyono; Suharto Suharto; Alaya Fadllu Hadi Mukhammad; Didik Nurhadiyanto; Arianto Leman Sumowidagdo
Indonesian Journal of Physics and Nuclear Applications Vol 3 No 1 (2018)
Publisher : Fakultas Sains dan Matematika Universitas Kristen Satya Wacana

Collimator is a tube that functions to direct neutrons generated by a nuclear reactor for BNCT (Boron Neutron Capture Therapy Cancer). Appropriate design of the collimator for BNCT application is a tube with an inner diameter of 16 cm, an outer diameter of 19 cm and a length of 13 cm total with 12 pieces with nickel purity above 95%. Manufacturing of the BNCT collimator will be planned using centrifugal casting method and smelting of nickel with electrical arc (EA) furnace. This article reports on the smelting process of nickel, setting the parameters of the electrical arc furnace, and the chemical composition of the nickel. Results of the study show that nickel with purity 98% can be melted perfectly using the EA Furnace with a current of 600-800 A and a pouring temperature of 1600°C. The fluidity of nickel can hold up to 1 minute at a 35°C environment that allows for the centrifugal casting process. The chemical composition of the nickel before being melted is Ni (98.89%), Si (0.79%), S (0.17%), and Fe (0.15%) and after being melted is Ni (97.89%), Si (0.92%), S (0.26%), and Fe (0.90%). The chemical composition of the nickel after smelting in an EA Furnace meets the requirements of BNCT collimator.

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

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.

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