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9 results on '"Kiswanta, Kiswanta"'

1. Requirement analysis for hardware and software design on FPGA-based power channel system of SMR NPP.

Author

Maerani, Restu, Kiswanta, Kiswanta, Deswandri, Deswandri, Gusman, Ranji, Rahmatullah, Helmi Fauzi, and Bakhri, Syaiful

Subjects
*SOFTWARE architecture, *DESIGN software, *REQUIREMENTS engineering, *FIELD programmable gate arrays, *LIGHT water reactors, *MICROPROCESSORS
Abstract

The power channel measurement tools design is an effort to improve performance and safety in a nuclear reactor, in helping operators to monitor the status of the reactor. In this design, Field Programmable Gates Array (FPGA)-based system will be implemented in the power channel measurement tool design for Small Modular Reactor (SMR) reactor type. The first step that must be considered is to meet the criteria of requirements related to the design of software and hardware that will be used in the design of power channel measurement tools for SMR. FPGAs have not been widely applied to nuclear reactors in general, but to increase security of the reactor, especially with hardware-based systems, it is expected to prevent cyber-attacks, to reduce common cause failure (CCF), software obsolescence on microprocessor-based systems is also more expensive, and reduces system complexity. Therefore, verifying the software and hardware design requirements in this design must be carried out to meet the SMR NPP design criteria, especially to meet its performance when compared to microprocessor-based systems. Because this SMR NPP are planned to be developed in Indonesia, the requirements should be referred from BAPETEN as the regulatory body in Indonesia. BAPETEN and International Atomic Energy Agency (IAEA) generally discuss a lot for large Light Water Reactor (LWR) type reactors, therefore, here it is necessary to study more deeply for its use in SMR reactors. Since the monitoring process also related to the Human Machine Interface design (HMI), therefore a requirement traceability diagram are made to ensure that all the criteria and requirements have been met. [ABSTRACT FROM AUTHOR]

Published
2024
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2. Gamma heating measurement of 15 MW RSG G.A. siwabessy silicide core.

Author

Rohanda, Anis, Pardi, Pardi, Haryanto, Dwi, Kiswanta, Kiswanta, and Waris, Abdul

Subjects
CALORIMETRY, RESEARCH reactors, GAMMA rays, ATOMIC number, IRON, SILICIDES
Abstract

The G.A. Siwabessy Multi-Purpose Reactor (RSG-GAS) is a research reactor that acts as a national facility for irradiating materials. One of the effects caused when a material is exposed to high-intensity gamma radiation is the generation of gamma heating. Gamma heating information is very important and used for the safety analysis of irradiation facilities such as research reactors. Gamma heat can be determined using measurements and calculations. In this research, gamma heating measurements have been carried out at the Central Irradiation Position (CIP) of the RSG-GAS silicide core at a power of 15 MW as a regular power level by using a gamma calorimeter. Measurements were made with four types of calorimeters, namely graphite (C), aluminum (Al), iron (Fe), and zirconium (Zr) absorbent materials. The measurement results are compared with the calculation results using the GAMSET program. The measured by each type of calorimeter are 2.2 W/g (C), 2.25 W/g (Al), 2.58 W/g (Fe), and 3.21 W/g (Zr). In general, the value of the gamma heating measured increases in proportion to the increase in the atomic number of the calorimeter absorbent material. Despite having the same trend, the measurement results also show differences with the GAMSET simulation results which are thought to be caused by the lack of accuracy in calculations at medium and high energy levels and the ideal conditions that are difficult to achieve from the calculation parameters used in GAMSET. [ABSTRACT FROM AUTHOR]

Published
2023
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6. SIMULASI BALANCE OF PLANT SISTEM PENDINGIN RDE MENGGUNAKAN FLOWNEX

Author

Arief Adityas Budiman, Kiswanta Kiswanta, and Muhammad Subekti

Subjects
General Medicine
Abstract

Reaktor Daya Eksperimental (RDE) adalah reaktor daya non komersial dan kogenerasi berbasis pendingin gas dan moderator grafit yang direncanakan dibangun di Indonesia. Daya listrik yang direncanakan maksimal 10,0 MWatt. Dengan adanya reaktor ini maka SDM Indonesia akan dapat memiliki pengalaman dalam menguasai teknologi reaktor daya jenis pendingin gas dan mendukung proyek pembangunan PLTN (reaktor daya komersial) yang memerlukan persiapan matang. Keselamatan merupakan aspek yang mendapat perhatian utama dalam Instalasi RDE. Instalasi RDE didesain, dibangun dan dioperasikan berdasarkan ketentuan-ketentuan, peraturan-peraturan dan standar-standar ( codes and standards ) yang harus diikuti, yang secara terus-menerus diperbarui dengan mempertimbangkan pengalaman-pengalaman yang diperoleh selama membangun dan mengoperasikan Instalasi RDE yang ada. Oleh karena itu akan dilakukan penelitian kajian desain Balance of Plant Sistem Pendingin RDE. Tujuan penelitian ini adalah melakukan simulasi dan kajian Balance of Plant Sistem Pendingin RDE dengan software Flownex untuk memahami aspek keselamatannya. Metode penelitian dilakukan dengan melakukan kajian pustaka, pemodelan, analisis dan review desain Balance of Plant sistem pendingin RDE dengan menggunakan software Flownex. Hasil penelitian menunjukkan bahwa validasi model termodinamika terhadap data Brayton diperoleh kesalahan relatif terbesar 2,39 % sehingga valid untuk digunakan dalam analisis termodinamika desain RDE 10 MW. Peningkatan laju alir pendingin primer dari 4,3 kg/s sampai dengan 5,5 kg/s diikuti kenaikan energi yang diperlukan untuk proses kompresi dari 2,47 MW sampai dengan 3,32 MW sehingga terjadi peningkatan EUF dari 29,17% sampai dengan 55,92%. Kata kunci : Flownex; pemodelan; simulasi; Sistem pendingin RDE

Published
2021

7. RANCANG BANGUN PANEL KONTROL SELENOID VALVE SISTEM TERBUKA BERBASIS PROGRAM DAN MANUAL PADA UNTAI UJI BETA (UUB)

Author

Kiswanta Kiswanta

Abstract

Untai Uji BETA (UUB) adalah sarana eksperimen yang dapat digunakan untuk mempelajari berbagai fenomena termohidroulika pada reaktor nuklir. Konfigurasi dasar UUB yaitu sistem pemanas (alat uji) dan sistem sirkulasi air. Rancangan dibuat untuk mengatur sistem sirkulasi air pada UUB dengan menggunakan sistem program dan manual yang mengatur selenoid valve. Metode yang telah dilakukan meliputi: (1) Perancangan sistem program dan manual yang mengatur selenoid valve. (2) Pembuatan sistem program menggunakan PLC melalui Programming Console. (3) membuat desain panel dilanjutkan dengan perakitan. (5) Pembuatan prosedur pengoperasian panel. (6) Tahap pengujian panel dan selenoid valve. Kesimpulan: sistem manual dibuat diluar aturan yang dibuat sistem program untuk mengatur selenoid valve.

Published
2018

8. Experimental Study of Quenching Process During Bottom Reflooding Using 'Queen' Test Section

Author

S. Edy, H. Ismu, P. Joko, Mulya Juarsa, Kiswanta Kiswanta, and Anhar Riza Antariksawan

Subjects
Convection, Quenching, Nuclear and High Energy Physics, Radiation, experiment, Chemistry, quenching, Thermodynamics, lcsh:TK9001-9401, Leidenfrost effect, Volumetric flow rate, Nuclear Energy and Engineering, Heat flux, Boiling, Heat transfer, lcsh:Nuclear engineering. Atomic power, Radiology, Nuclear Medicine and imaging, reflooding, Waste Management and Disposal, Nucleate boiling
Abstract

Phenomenon of quenching of hot fuels in core during bottom reflooding following loca event is investigated in order to understand the performance cooling process. the study is conducted experimentally using queen test section which allow study of rod surface temperature histories based on which the heat fluxes are estimated. the visual observation is also done to study the boiling regimes. the test variables are initial rod temperature, i.e. 400 o c, 500 o c and 600 o c, and coolant flow rate, i.e. 0,01kg/s, 0.02 kg/s and 0.04 kg/s with constant water inlet temperature of 30 o c. the results shows different heat transfer regimes such as film boiling, transition boiling, nucleate boiling and convective single phase heat transfer regimes. for specified initial rod temperature, the higher flow rate provides high rewet velocity and higher maximum heat flux, then quenching process is more effective.

Published
2011

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