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Spent nuclear fuel (SF) handling is one of the main problems in the development of Nuclear Power Plant. Spent PWR fuel recycling in CANDU reactors without fissile material separation, led to the idea of recycling LWR waste in LWR reactors known as SUPEL (Straight Utilization of sPEnt LWR Fuel in LWR...
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| Language: | Indonesia |
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| Institution: | Institut Teknologi Bandung |
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id-itb.:186692017-09-27T11:45:16Z#TITLE_ALTERNATIVE# SAIDATUNINGTYAS (NIM : 10207100); Pembimbing : Dr. Abdul Waris, IFA Indonesia Final Project INSTITUT TEKNOLOGI BANDUNG https://digilib.itb.ac.id/gdl/view/18669 Spent nuclear fuel (SF) handling is one of the main problems in the development of Nuclear Power Plant. Spent PWR fuel recycling in CANDU reactors without fissile material separation, led to the idea of recycling LWR waste in LWR reactors known as SUPEL (Straight Utilization of sPEnt LWR Fuel in LWR system) scenario. This scenario is done by mixing SF and new fuels (UO2) in certain compositions. In this final project, SUPEL scenario has been implemented in BWR reactor using SRAC program 2006 and nuclides data library JENDL-4.0. The results show that the most suitable composition are the fuel type 1 with 6% uranium enrichment, the fuel type 5 with 7% uranium enrichment and the fuel type 8 with 8% enrichment. The use of higher initial enrichment in BWR will magnify the value of keff, adding SF fraction to more than 19%, and produce the lower density of plutonium and Minor Actinides except for several nuclides such as Np-237 and Pu-239. text |
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Spent nuclear fuel (SF) handling is one of the main problems in the development of Nuclear Power Plant. Spent PWR fuel recycling in CANDU reactors without fissile material separation, led to the idea of recycling LWR waste in LWR reactors known as SUPEL (Straight Utilization of sPEnt LWR Fuel in LWR system) scenario. This scenario is done by mixing SF and new fuels (UO2) in certain compositions. In this final project, SUPEL scenario has been implemented in BWR reactor using SRAC program 2006 and nuclides data library JENDL-4.0. The results show that the most suitable composition are the fuel type 1 with 6% uranium enrichment, the fuel type 5 with 7% uranium enrichment and the fuel type 8 with 8% enrichment. The use of higher initial enrichment in BWR will magnify the value of keff, adding SF fraction to more than 19%, and produce the lower density of plutonium and Minor Actinides except for several nuclides such as Np-237 and Pu-239. |
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Final Project |
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SAIDATUNINGTYAS (NIM : 10207100); Pembimbing : Dr. Abdul Waris, IFA |
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SAIDATUNINGTYAS (NIM : 10207100); Pembimbing : Dr. Abdul Waris, IFA #TITLE_ALTERNATIVE# |
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SAIDATUNINGTYAS (NIM : 10207100); Pembimbing : Dr. Abdul Waris, IFA |
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SAIDATUNINGTYAS (NIM : 10207100); Pembimbing : Dr. Abdul Waris, IFA |
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https://digilib.itb.ac.id/gdl/view/18669 |
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1820745949159358464 |