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Ign. Djoko Irianto
Badan Tenaga Nuklir Nasional
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ANALISIS PERHITUNGAN KOEFISIEN REAKTIVITAS DOPPLER PARTIKEL TRISO REAKTOR TEMPERATUR TINGGI Zuhair Zuhair; Suwoto Suwoto; Ign. Djoko Irianto
Jurnal Pengembangan Energi Nuklir Vol 13, No 1 (2011): Juni 2011
Publisher : Pusat Kajian Sistem Energi Nuklir, Badan Tenaga Nuklir Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/jpen.2011.13.1.1456

Abstract

ABSTRAKANALISIS PERHITUNGAN KOEFISIEN REAKTIVITAS DOPPLER PARTIKEL TRISO REAKTOR TEMPERATUR TINGGI. Salah satu aspek keselamatan melekat HTR didasarkan pada koefisien reaktivitas temperatur bahan bakar dan moderator yang negatif. Koefisien temperatur bahan bakar dikenal dengan sebutan koefisien reaktivitas Doppler. Makalah ini mendiskusikan perhitungan koefisien reaktivitas Doppler partikel TRISO dalam matriks grafit dengan program transport Monte Carlo MCNP5 dan pustaka tampang lintang energi kontinu ENDF/B-VII. Partikel TRISO dimodelkan dengan kisi BCC dimana kernel dan keempat lapisan coating disimulasikan secara eksplisit. Serangkaian perhitungan dikerjakan dengan fraksi packing TRISO yang berbeda dan temperatur kernel, TF, yang berbeda pula. Temperatur matriks grafit, TM, dijaga konstan pada 1200K. Hasil perhitungan memperlihatkan semakin tinggi temperatur bahan bakar, semakin rendah nilai kritikalitas (k) partikel TRISO. Dengan bertambahnya temperatur bahan bakar, reaktivitas partikel TRISO menurun untuk seluruh fraksi packing TRISO yang dipertimbangkan. Hasil perhitungan juga memperlihatkan koefisien reaktivitas Doppler menurun dengan naiknya temperatur bahan bakar dan meningkat dengan bertambahnya fraksi packing TRISO. Dapat disimpulkan bahwa, pemilihan fraksi packing TRISO dan temperatur operasi merupakan opsi penting dalam analisis desain keselamatan melekat reaktor temperatur tinggi.Kata kunci: koefisien reaktivitas Doppler, partikel TRISO, BCC, MCNP5, ENDF/B-VII ABSTRACTANALYSIS ON THE CALCULATION OF DOPPLER REACTIVITY COEFFISIENT FOR TRISO PARTICLE OF HIGH TEMPERATURE REACTOR. One of HTR inherent safety aspects is based on the negative fuel and moderator temperature reactivity coefficients. Fuel temperature coefficient is known as the Doppler reactivity coefficient. This paper discusses the calculation of the Doppler reactivity coefficient for TRISO particles in graphite matrix with MCNP5 Monte Carlo transport code and ENDF/B-VII continuous energy cross section library. TRISO particles are modeled as BCC lattice where the kernel and four coating layers are simulated explicitly. A series of calculations were done with different TRISO packing fraction and different temperature of the kernel, TF. Temperature graphite matrix, TM, is kept constant at 1200K. The calculation results show the higher the fuel temperature, the lower value of TRISO particles criticality (k). The increasing temperature of fuel, TRISO particle reactivity decreases for all considered TRISO packing fraction. The calculation results show also the Doppler reactivity coefficient decreases with rising of fuel temperature and increases with increasing of TRISO packing fraction. It can be concluded that the choice of TRISO packing fraction and operational temperature are important option in inherent safety design analysis of high temperature reactor.Keywords: Doppler reactivity coefficient, TRISO particle, BCC, MCNP5, ENDF/B-VI
STUDI OPTIMASI MODERASI NEUTRON DALAM TERAS HTR PEBBLE BED Zuhair Zuhair; Suwoto Suwoto; Ign. Djoko Irianto
Jurnal Pengembangan Energi Nuklir Vol 12, No 2 (2010): Desember 2010
Publisher : Pusat Kajian Sistem Energi Nuklir, Badan Tenaga Nuklir Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/jpen.2010.12.2.1452

Abstract

ABSTRAKSTUDI OPTIMASI MODERASI NEUTRON DALAM TERAS HTR PEBBLE BED. Dalam HTR pebble bed, moderasi neutron sangat dipengaruhi oleh rasio bola moderator (M) dan bola bahan bakar (F) yang terdapat dalam teras reaktor. Moderasi optimal dapat dicapai dengan mengatur rasio F/M, namun kombinasi bola dengan rasio F/M lebih dari 1:1 dalam teras reaktor pebble bed menimbulkan masalah dalam perhitungan. Metode untuk menyelesaikan masalah ini didiskusikan dalam makalah ini. Optimasi moderasi dalam teras HTR pebble bed diinvestigasi dengan melakukan serangkaian perhitungan menggunakan program transport Monte Carlo MCNP5. Model bola bahan bakar dengan kernel UO2 dan bola moderator dengan densitas grafit spesifik dipilih agar sesuai dengan desain mutakhir HTR pebble bed. Pustaka data nuklir energi kontinu ENDF/B-VI dimanfaatkan untuk melengkapi analisis optimasi moderasi. Hasil perhitungan memperlihatkan bahwa nilai keff memiliki tendensi semakin meningkat dengan bertambahnya rasio F/M kemudian menurun secara perlahan setelah mencapai nilai tertentu. Rasio F/M yang besar menyebabkan nilai keff berkurang karena tangkapan resonansi neutron (under-moderated). Rasio F/M yang kecil menyebabkan nilai keff berkurang karena absorpsi neutron parasitik oleh moderator (over-moderated). Dari seluruh hasil perhitungan dapat disimpulkan bahwa optimasi moderasi neutron dalam teras HTR pebble bed dicapai dengan kombinasi bola yang dispesifikasikan oleh rasio F/M 3:2.Kata kunci: moderasi neutron, faktor multiplikasi, HTR pebble bed, MCNP5 ABSTRACTSTUDY ON OPTIMIZING NEUTRON MODERATION IN HTR PEBBLE-BED CORE. In HTR pebble bed, the neutron moderation is strongly influenced by the ratio of the fuel pebbles (F) and the moderator pebbles (M) contained in the reactor core. Optimum moderation can be achieved by adjusting the ratio F/M, but the combination of the pebble with the ratio of F/M more than 1:1 in pebble bed reactor core raises a problem in the calculation. This paper discusses a method to solve this problem. Optimizing neutron moderation in the HTR pebble bed core was investigated by conducting a series of calculations using Monte Carlo transport code MCNP5. The model of the fuel pebble with UO2 kernel and the moderator pebble with specific density of graphite was chosen to fit the current design of HTR pebble bed. The continuous energy nuclear data library ENDF/B-VI was used to complete the analysis of moderation optimization. The calculation results show that the values of keff tend to increase in line with the rise of ratio of F/M and go down slightly after a particular value. A large ratio of F/M causes a decrease in keff value because of the resonance neutron capture (under-moderated). A small ratio of F/M causes a decrease in keff value because of parasitic neutron absorption by the moderator (over-moderated). From all calculation results it can be concluded that the neutron moderation optimization of HTR pebble bed core is achieved with a combination of pebbles which is specified by the ratio of F/M 3:2.Keywords: neutron moderation, multiplication factor, HTR pebble bed, MCNP5
Co-Authors Suwoto Suwoto Zuhair Zuhair