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RANCANGAN KONSEPTUAL REAKTOR SUBKRITIK UNTUK KAJIAN TRANSMUTASI LIMBAH PLTN BERBASIS REAKTOR KARTINI Syarip, Syarip; Sutondo, Tegas; Triyono BS, Edi
Jurnal Pengembangan Energi Nuklir Vol 15, No 2 (2013): Desember 2013
Publisher : Pusat Kajian Sistem Energi Nuklir, Badan Tenaga Nuklir Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (746.442 KB) | DOI: 10.17146/jpen.2013.15.2.1501

Abstract

ABSTRAKRANCANGAN KONSEPTUAL REAKTOR SUBKRITIK UNTUK KAJIAN TRANSMUTASI LIMBAH PLTN BERBASIS REAKTOR KARTINI. Disajikan hasil rancangan konseptual berupa kajian perhitungan aspek teoretis dan analisis kelayakan teknis suatu sistem reaktor subkritik dengan sumber neutron luar berasal dari akselerator (Small Scale Reactor Accelerator Driven System / SS-RADS) berbasis reaktor Kartini. Model teras reaktor berbentuk silinder berisi aktinida minor (MA) yang dikelilingi oleh bahan bakar reaktor Kartini. Modul ADS-CDS yang berbasis pada program SRAC digunakan untuk kajian aspek neutronik. Hasil perhitungan menunjukkan bahwa keberadaan unsur MA akan memberikan reaktivitas positif yang nilainya semakin besar dengan meningkatnya konsentrasi MA. Program komputer ORIGEN2 digunakan untuk perhitungan transmutasi radioinuklida MA sebagai fungsi energi dan fluks neutron. Hasil analisis menunjukkan bahwa transmutasi radionuklida MA tersebut akan berlangsung lebih optimum dengan neutron termal dibandingkan dengan neutron cepat. Unsur MA yang paling banyak mengalami transmutasi adalah Am241 yaitu dengan laju transmutasi 50% selama 1000 hari operasi pada tingkat fluks neutron termal 1013 n/cm2 s, dan yang paling sedikit mengalami transmutasi adalah Cm244 yaitu hanya 0,5%, serta laju transmutasi rerata total 32%. Dapat disimpulkan bahwa SS-RADS berbasis reaktor Kartini dapat digunakan untuk eksperimen transmutasi limbah nuklir (MA) jika tingkat fluks neutron termalnya 1013 n/cm2 s.Kata kunci: PLTN, reaktor subkritik, limbah nuklir, aktinida minor ABSTRACTCONCEPTUAL DESIGN OF SUBCRITICAL ASSEMBLY FOR NPP NUCLEAR WASTE TRANSMUTATION STUDY BASED ON KARTINI REACTOR. The conceptual design theoretical study and technical feasibility analysis results of subcritical assembly (Small Scale Reactor Accelerator Driven System /SS-RADS) based on Kartini reactor is presented in this paper. The reactor core model is a cylindrical containing minor actinide (MA) surrounded by Kartini reactor fuels. ADS-CDS module based on SRAC code was used to study neutronic aspect. Calculation results show that the present of MA as nuclear waste will provide positive reactivity value and will increasing according to its concentration. The ORIGEN2 computer code was used to calculate MA transmutation as a function of neutron energy and flux. The analysis results show that the optimum waste transmutation of the above radionuclide will achieved with thermal neutron (thermal reactor), instead of fast neutron. The most transmuted element is Am241 with 50% transmutation rate at thermal neutron flux of 1013 n/cm2 s, the lowest transmuted is Cm244 i.e. only 0,5%, and total average transmutation is 32%. It can be concluded that the SS-RADS based on Kartini reactor can be used for nuclear waste transmutation study if the thermal neutron flux level is around 1013 n/cm2 s.Keywords: nuclear power plants, subcritical reactor, nuclear waste, minor actinide
ANALYSES OF FUEL BURNUP CALCULATIONS OF KARTINI REACTOR BASED ON THE NEW CALCULATION SCHEME Sutondo, Tegas
GANENDRA Majalah IPTEK Nuklir Volume 17 Nomor 2 Juli 2014
Publisher : PSTA BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (625.112 KB) | DOI: 10.17146/gnd.2014.17.2.2801

Abstract

ABSTRACT ANALYSES OF FUEL BURNUP CALCULATIONS OF KARTINI REACTOR BASED ON THE NEW CALCULATION SCHEME. It has been described a new scheme of fuel burnup calculation, intended to improve the present practice used at Kartini reactor. The improvement includes the use of power distributions, which will be used as the base for estimating the burnup of each individual fuel element, and the inclusion of epithermal neutron which will affect to the burnup rates and the total fuel consumed. A small computation program was then made to perform calculations based on the two calculation schemes, and to see the differences. The results indicate that the proposed scheme results in higher estimated value against that of the present scheme, and the differences tends to increase linearly with the cumulative burnups. For each cumulative burnup of 30 MWD the difference could reach about 9.87 % which is around 3.7 gram for the whole core. It can be concluded that the proposed approach could improve the present’s practice of burnup estimation, especially for each individual fuel element which is important to the in-core fuel management program.
METODE SEMIEMPIRIS UNTUK MENENTUKAN KOMPOSISI ISOTOP URANIUM Sutondo, Tegas
GANENDRA Majalah IPTEK Nuklir Volume 11 Nomor 2 Juli 2008
Publisher : PSTA BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (200.358 KB) | DOI: 10.17146/gnd.2008.11.2.140

Abstract

METODE SEMIEMPIRIS UNTUK MENENTUKAN KOMPOSISI ISOTOP URANIUM. Pada perhitungan desain reaktornuklir, sering diperlukan beberapa variasi tingkat pengkayaan U235. Hal ini akan berpengaruh terhadap komposisi 3isotop uranium utama yaitu U234, U235 dan U238 untuk tingkat pengkayaan U235 yang diinginkan. Mengingat terbatasnyadata komposisi yang tersedia maka perlu dilakukan suatu cara pendekatan, untuk memperkirakan komposisi ke-3isotop tersebut, sesuai dengan nilai tingkat pengkayaan U235 yang diinginkan. Makalah ini menyajikan dasar teori yangdigunakan untuk menyusun suatu rumus semi empiris untuk memperkirakan komposisi 3 isotop uranium sebagaifungsi nilai pengkayaan U235, yang diperoleh berdasarkan data eksperimen yang tersedia. Berdasarkan data yangtersedia, serta kelangkaan data untuk rentang pengkayaan antara 3,5 % hingga 12 %, disimpulkan bahwa untukisotop U235 perlu digunakan 2 persamaan linear yang berbeda yaitu untuk pengkayaan ≤ 3,5 % dan ≥ 3,5 %. Untukisotop U234 satu fungsi polinomial orde 4 bisa digunakan secara baik untuk seluruh pengkayaan dalam rentang 0,711% hingga 20 %, sedangkan untuk pengkayaan yang lebih tinggi (> 20 %), maka lebih baik digunakan pendekatanpersamaan power fitting. Komposisi isotop U238 selanjutnya dapat ditentukan dari komposisi isotop U235 dan U234 untukpengkayaan U235 yang diinginkan.
REACTIVITY INSERTION ACCIDENT ANALYSIS OF KARTINI REACTOR Sutondo, Tegas
GANENDRA Majalah IPTEK Nuklir Volume 14 Nomor 2 Juli 2011
Publisher : PSTA BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (551.22 KB) | DOI: 10.17146/gnd.2011.14.2.40

Abstract

REACTIVITY INSERTION ACCIDENT ANALYSIS OF KARTINI REACTOR. A transient analysis of reactivity insertionaccident of Kartini reactor during start up from the minimum critical condition has been performed to estimate the effect onthe fuel temperature increase. Two cases of reactivity insertion limits had been assumed in this study i.e. the reactivityinsertions were limited by the actuation of overpower trip system (110 %) for the 1st case and by manual scram when thecontrol rod reached the 100 % UP position, assuming the overpower trip system was failed to function for the 2nd case.Adiabatic condition was assumed in this study, to get the most severe condition. The result shows that based on theassumed power level of trip setting for the 1st case, the total reactivity insertion was 0.82 $, corresponding to the reactorperiod of about 2 s and causing the maximum fuel temperature increase of around 11 oC or the maximum fuel temperature of45 oC. For the 2nd case the total reactivity insertion at the trip point was 1.367 $, resulting in the maximum fuel temperatureincrease of about 103 oC or maximum fuel temperatur of around 137 oC which is still far below the defined design limit of1115 oC for transient condition and 700 oC for steady state as well. This result concludes that by limiting the available coreexcess of reactivity at reasonably low, it could prevent the fuel from possible of undergoing an excessive temperatureincrease, during the postulated reactivity insertion accident.Keywords: Transient analysis, reactivity insertion, accident, reactor kartini, fuel temperature.
BEAM MODELING FOR PGNAA EXPERIMENTAL FACILITY AT KARTINI REACTOR Sutondo, Tegas
GANENDRA Majalah IPTEK Nuklir Volume 18 Nomor 2 Juli 2015
Publisher : PSTA BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (473.144 KB) | DOI: 10.17146/gnd.2015.18.2.2817

Abstract

BEAM MODELING FOR PGNAA EXPERIMENTAL FACILITY AT KARTINI REACTOR. A feasibility study on possible use of Kartini reactor’s beam port for Prompt Gamma Neutron Activation Analysis (PGNAA) experimental facility is going on. This work is part of the revitalization program activities of Kartini research reactor, including utilization of the available irradiation facilities. This paper presents results of beam modeling at the tangential beam port to get neutron beam meeting the specified criteria. The study was conducted by means of simulations using MCNPX code. The result concludes that there are several possible variations of collimator models that can provide neutron beam meeting the specified criteria and that tangential beam port is considered to be feasible enough for the purpose of PGNAA experimental facility