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All Journal SIGMA EPSILON - Majalah Ilmiah Teknologi Keselamatan Nuklir Jurnal Teknologi Reaktor Nuklir Tri Dasa Mega Urania Jurnal Ilmiah Daur Bahan Bakar Nuklir
Ihda Husnayani
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Computer Science & IT Energy Materials Science & Nanotechnology

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CALCULATION OF RADIONUCLIDE CONTENT OF NUCLEAR MATERIALS USING ORIGEN2.1 COMPUTER CODE Ihda Husnayani
SIGMA EPSILON - Buletin Ilmiah Teknologi Keselamatan Reaktor Nuklir Vol 19, No 1 (2015): Februari 2015
Publisher : Badan Tenaga Nuklir Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (511.476 KB) | DOI: 10.17146/sigma.2015.19.1.2893

Abstract

Nuclear materials contain a number of radionuclides produced from radioactive decay process. The composition of these radionuclides which are accumulated in-side the nuclear materials changes over the time. The calculation of radionuclide composition inside nuclear materials is very important especially in the aspect of nuclear reactor safety evaluation, nu-clear fuel behavior evaluation, and radioactive waste management. One method to calculate radionu-clide content of nuclear materials is by using ORIGEN2.1 computer code. Beside radionuclide com-position, this code can also calculate some characteristics related to decay process such as total radio-activity, decay heat, and neutron flux. This paper is a literature study about ORIGEN2.1 computer code. A brief description of ORIGEN2.1 and its use for calculating radionuclide content of nuclear materials are presented. Radionuclide content produced from californium-252 decay was chosen as a simple case solved by ORIGEN2.1. Californium-252 was simulated to undergo decay for 10 years. The variables which are calculated by ORIGEN2.1 in this case are radionuclide composition, total radioactivity, total alpha radioactivity, and neutron flux. From the results of this simulation, it is shown that small amount of californium-252 produces high neutron intensity so that it can be used as a reliable neutron source for many applications.
CHARACTERISTICS OF RADIONUCLIDES ON THORIUM-CYCLE EXPERIMENTAL POWER REACTOR SPENT FUEL R. Andika Putra Dwijayanto, S.T.; Ihda Husnayani; Zuhair Zuhair
Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol 25, No 2 (2019): Juni, 2019
Publisher : website

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (674.731 KB) | DOI: 10.17146/urania.2019.25.2.5525

Abstract

CHARACTERISTICS OF RADIONUCLIDES ON THORIUM-CYCLE EXPERIMENTAL POWER REACTOR SPENT FUEL. There are several options of nuclear fuel utilisation in the HTGR-based Experimental Power Reactor (Reaktor Daya Eksperimental/RDE). Although mainly RDE utilises low enriched uranium (LEU)-based fuel, which is the most viable option at the moment, it is possible for RDE to utilise other fuel, for example thorium-based and possibly even plutonium-based fuel. Different fuel yields different spent fuel characteristics, so it is necessary to identify the characteristics to understand and evaluate their handling and interim storage. This paper provides the study on the characteristics of thorium-fuelled RDE spent fuel, assuming typical operational cycle. ORIGEN2.1 code is employed to determine the spent fuel characteristics. The result showed that at the end of the calculation cycle, each thorium-based spent fuel pebble generates around 0,627 Watts of heat, 28 neutrons/s, 8.28x1012 photons/s and yield 192.53 curies of radioactivity. These higher radioactivity and photon emission possibly necessitate different measures in spent fuel management, if RDE were to use thorium-based fuel. Tl-208 activity, which found to be emitting potentially non-negligible strong gamma emission, magnified the requirement of proper spent fuel handling especially radiation shielding in spent fuel cask.Keywords: RDE, spent fuel, thorium, HTGR, Tl-208.
THE PRELIMINARY STUDY ON IMPLEMENTING A SIMPLIFIED SOURCE TERMS ESTIMATION PROGRAM FOR EARLY RADIOLOGICAL CONSEQUENCES ANALYSIS Theo Alvin Ryanto; Jupiter Sitorus Pane; Muhammad Budi Setiawan; Ihda Husnayani; Anik Purwaningsih; Hendro Tjahjono
JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA Vol 25, No 2 (2023): June 2023
Publisher : Pusat Teknologi Dan Keselamatan Reaktor Nuklir (PTKRN)

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/tdm.2023.6869

Abstract

Indonesia possesses numerous potential sites for nuclear power plant development. A fast and comprehensive radiological consequences analysis is required to conduct a preliminary analysis of radionuclide release into the atmosphere, including source terms estimation. One simplified method for such estimation is the use of the Relative Volatility approach by Kess and Booth, published in IAEA TECDOC 1127. The objective of this study was to evaluate the use of a simple and comprehensive tool for estimating the source terms of planned nuclear power plants to facilitate the analysis of radiological consequences during site evaluation. Input parameters for the estimation include fuel burn-up, blow-down time, specific heat transfer of fuel to cladding, and coolant debit, using 100 MWe PWR as a case study. The results indicate a slight difference in the calculated release fraction compared to previous calculations, indicating a need to modify Keywords: Source terms, Relative volatility, Release fraction, PWR, SMART
Co-Authors Anik Purwaningsih Hendro Tjahjono Jupiter Sitorus Pane Muhammad Budi Setiawan R. Andika Putra Dwijayanto, S.T. Theo Alvin Ryanto Zuhair Zuhair