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All Journal SIGMA EPSILON - Majalah Ilmiah Teknologi Keselamatan Nuklir Jurnal Teknologi Reaktor Nuklir Tri Dasa Mega
Mike Susmikanti
Pusat Teknologi dan Keselamatan Reaktor, BATAN
Computer Science & IT Energy Materials Science & Nanotechnology

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EVALUASI SISA UMUR KOMPONEN SISTEM KESELAMATAN REAKTOR RISET RSG-GAS Mike Susmikanti; Entin Hartini; Abdul Hafid; Geni Rina Sunaryo; Endiah Puji Hastuti; Sriyono Sriyono; Muhammad Subekti; Aep Saefudin; Purwadi Purwadi
SIGMA EPSILON - Buletin Ilmiah Teknologi Keselamatan Reaktor Nuklir Vol 24, No 2 (2020): November 2020
Publisher : Badan Tenaga Nuklir Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/sigma.2020.24.2.5863

Abstract

Umur komponen merupakan hal terpenting bagi status komponen setelah beroperasi sekian lama dalam kurun waktu tertentu sehingga dapat diketahui apakah masih dapat berfungsi dengan baik dan apakah perlu dilakukan perawatan secara kontinyu. Saat ini umur komponen dalam kaitannya dengan keselamatan dan manajemen penuaan RSG-GAS masih belum dievaluasi khususnya untuk komponen yang mendukung sistim keselamatan. Penelitian ini bertujuan melakukan evaluasi umur komponen pendukung sistim keselamatan dalam kurun waktu tahun 2005-2015. Kegiatan penelitian meliputi pencarian informasi kegagalan, perbaikan dan perawatan komponen pendukung sistim keselamatan RSG-GAS pada teras nomor 55 - 88. Evaluasi umur komponen meliputi uji kecocokan (goodness of fit) dan karakteristik sebaran antara waktu kegagalan dan perbaikan. Selanjutnya dilakukan perhitungan fungsi peluang keandalan dan tingkat resiko yang berkaitan dengan faktor keselamatan, serta peluang komponen akan gagal pada waktu tertentu. Berdasarkan hasil evaluasi ini diperoleh bahwasanya perawatan secara berkala sangat diperlukan.Kata kunci : manajemen penuaan, umur komponen, komponen pendukung sistim keselamatan, kegagalan, perawatan, RSG-GAS
EVALUATION ON MECHANICAL FRACTURE OF PWR PRESSURE VESSEL AND MODELING BASED ON NEURAL NETWORK Mike Susmikanti; Roziq Himawan; Abdul Hafid; Entin Hartini
JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA Vol 18, No 2 (2016): Juni 2016
Publisher : Pusat Teknologi Dan Keselamatan Reaktor Nuklir (PTKRN)

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (1219.285 KB) | DOI: 10.17146/tdm.2016.18.2.2641

Abstract

ABSTRACT EVALUATION ON MECHANICAL FRACTURE OF PWR PRESSURE VESSEL AND MODELING BASED ON NEURAL NETWORK. The important component of the PWR is a pressure vessel. The material resistance in the pressure vessel needs to be evaluated. One way of evaluation is by the mechanical fracture analysis. The modeling needs to know the phenomena of the analysis result in general. A number of researches have been completed on the calculation of mechanical fracture in the pressure vessel with an internal load. The mechanical fracture was modeled using a neural network approach. In relation to the material resistance of the pressure vessel, which is used in PWR AP1000, the material must be evaluated because of the effect of the load. The modeling is needed to predict the effect of the load. The aim of this study is to evaluate the material resistance through mechanical fracture analysis because of the influence load on the pressure vessel on PWR AP1000. The material, which was observed, is SA 508. This analysis consists of the calculation of stress intensity factor and J-integral with some load at the crack propagation position. The fracture mechanic was analyzed by finite element simulation. The result of Stress Intensity factor and J-Integral was compared with fracture toughness to know the durability of the material. The modeling of  J-Integral and Stress Intensity Factor were obtained for some load based on neural network approach. Keywords: Material resistance, mechanical fracture, neural network, PWR, pressure vessel, crack propagation.   ABSTRAK EVALUASI FRAKTUR MEKANIK PADA BEJANA TEKAN PWR DAN PEMODELAN BERBASIS NEURAL NETWORK. Komponen penting dari PWR adalah  bejana tekan. Ketahanan bahan di bejana tekan perlu dievaluasi. Salah satu cara adalah dengan analisis fraktur mekanik. Pemodelan diperlukan untuk mengetahui fenomena hasil analisis pada umumnya. Terdapat penelitian untuk perhitungan fraktur mekanik dalam bejana tekan dengan beban internal. Penelitian lain adalah hasil dari fraktur mekanik dimodelkan menggunakan pendekatan jaringan syaraf. Sehubungan dengan ketahanan material dari bejana tekan yang digunakan dalam PWR AP1000, bahan harus dievaluasi karena efek dari beban. Pemodelan diperlukan untuk memprediksi pengaruh beban pada bahan dalam bejana tekan. Tujuan dari penelitian ini adalah untuk mengevaluasi ketahanan material melalui analisis fraktur mekanik karena pengaruh beban pada bejana tekan. Bahan yang diamati, adalah SA 508. Analisis ini terdiri dari perhitungan faktor intensitas tegangan dan J-integral dengan beberapa beban pada posisi perambatan retak. Fraktur mekanik dianalisis dengan metode elemen hingga. Hasil faktor intensitas tegangan dan J-Integral dibandingkan dengan ketangguhan patah untuk mengetahui daya tahan material. Pemodelan J-Integral dan faktor intensitas stres diperoleh untuk beberapa beban berdasarkan  jaringan saraf. Kata kunci: Ketahanan bahan, teknik patahan,  jaringan syaraf,  PWR,  bejana tekan, perambatan retak. 
STRAIN ANALYSIS OF REACTOR TYPE CORE STRUCTURES BY CONSIDERING UNCERTAINTIES OF GRAPHITE’S PROPERTIES Mike Susmikanti; Roziq Himawan; Jos Budi Sulistyo; Farisy Yogatama Sulistyo
JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA Vol 23, No 1 (2021): FEBRUARY 2021
Publisher : Pusat Teknologi Dan Keselamatan Reaktor Nuklir (PTKRN)

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/tdm.2021.23.1.6172

Abstract

The power reactor with high-temperature gas-cooled reactor (HTGR) technology uses uranium as the reactor fuel. The energy from fission is converted to electrical energy or used for other needs such as hydrogen production or other research activities at high temperatures of around 700 °C. This operation does not allow the use of metal as the core material for the reactor. The material that fits the requirements as a core structure is graphite. Graphite material has specific characteristics, namely the parameters of the modulus of elasticity, coefficient of thermal expansion, and the volume which changes due to temperature and neutron dose. Because the structure of the reactor core is a vital component in the reactor, this research will develop a method for the design of the reactor core structure with graphite material. The design method is based on "Design by Analysis" which specifically refers to the strain analysis on each of the reactor core components. The design method developed is based on the finite element method. The object of this research is the side reflector made from the Toyo Tanso IG-110 series graphite. Based on the analysis of heat distribution and heat stress for the material before the effect of neutron exposure, the temperature distribution on the side reflector was found, as well as the displacement and heat stress that occurs. isotropic properties, Young's modulus and Poisson’s ratio values can be verified and estimated. The purpose of this research is to analyze the strain of the reactor core structure by taking into account the uncertainty of the graphite properties. 
Co-Authors Abdul Hafid Abdul Hafid Aep Saefudin Endiah Puji Hastuti Entin Hartini Entin Hartini Farisy Yogatama Sulistyo Geni Rina Sunaryo Jos Budi Sulistyo Muhammad Subekti Purwadi Purwadi Roziq Himawan Roziq Himawan Sriyono Sriyono