<> <http://www.w3.org/2000/01/rdf-schema#comment> "The repository administrator has not yet configured an RDF license."^^<http://www.w3.org/2001/XMLSchema#string> .
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<http://digilib.unila.ac.id/id/eprint/61833> <http://purl.org/dc/terms/title> "PERHITUNGAN LAJU REAKSI NEUTRON DALAM REAKTOR SCWR\r\n(SUPERCRITICAL WATER REACTOR) MODEL PERANGKAT\r\n(ASSEMBLY) HEKSAGONAL BERBAHAN BAKAR URANIUM"^^<http://www.w3.org/2001/XMLSchema#string> .
<http://digilib.unila.ac.id/id/eprint/61833> <http://purl.org/ontology/bibo/abstract> "Telah dilakukan perhitungan laju reaksi fisi dan penangkapan neutron dengan\r\nfilter dan tanpa filter model geometri heksagonal menggunakan program SRAC\r\nkode REACT. Penelitian ini menggunakkan bahan bakar uranium-235 dan\r\nuranium-238. Hasil perhitungan Laju reaksi fisi pada material 1 dan material 3\r\ndengan menggunakan filter dan tanpa filter meningkat seiring dengan\r\nmeningkatnya nilai persentase pengayaan U\r\n\r\n235. Nilai tertinggi pada laju reaksi fisi\r\nneutron material 1 tanpa filter terdapat pada mesh ke-2 dengan pengayaan 1%\r\nyaitu sebesar 3,0747x10-2\r\n\r\nreaksi/cm3\r\n\r\ns. Sedangkan laju reaksi penangkapan\r\nneutron menggunakan filter meningkat seiring meningkatnya persentase pada U235\r\ndengan pengayaan 1% mesh ke-5 yaitu dengan nilai sebesar 9,8627 x10-2\r\nreaksi/cm3\r\n\r\ns. Kemudian Laju reaksi fisi neutron tanpa filter pada material 3\r\n\r\nmeningkat seiring dengan meningkatnya persentase pada pengayaan 1% mesh ke-\r\n5 yaitu sebesar 9,4778 x10-2\r\n\r\nreaksi/cm3\r\n\r\ns. Hal ini dikarenakan meningkatnya\r\npersentase pada pengayaan U235 pada pin bahan bakar. Sedangkan laju reaksi\r\n\r\npenangkapan menggunakan filter pada material 1 dengan persentase 1% mesh ke-\r\n2 memiliki nilai tertinggi dibandingkan dengan filter yaitu sebesar 9,8181 x10-2\r\n\r\nreaksi/cm3\r\ns.\r\n\r\nKata kunci : Uranium, SCWR, Laju Reaksi Neutron dan SRAC.\r\nCalculation of the rate of fission and neutron capture reactions with a filter and\r\nwithout a filter has been carried out using a hexagonal geometry model using the\r\nREACT code SRAC program. This research uses uranium-235 and uranium-238\r\nas fuel. Calculation results The rate of fission reaction in material 1 and material\r\n3 using a filter and without a filter increases with the increase in the percentage\r\nvalue of U235 enrichment. The highest value for the neutron fission reaction rate\r\nof material 1 without a filter is found in the second mesh with 1% enrichment,\r\nwhich is 3.0747x10-2\r\n\r\nreactions/cm3\r\n\r\ns. Meanwhile, the rate of neutron capture\r\nreaction using a filter increases with the increase in the percentage of U235 with\r\n1% enrichment of the 5th mesh, with a value of 9.8627 x10-2\r\n\r\nreactions/cm3\r\ns. Then\r\nthe unfiltered neutron fission reaction rate on material 3 increased along with the\r\nincreasing percentage in the 5th 1% enrichment mesh, which was 9.4778 x10-2\r\nreactions/cm3\r\n\r\ns. This is due to the increasing percentage of U235 enrichment in\r\nthe fuel pin. While the rate of capture reaction using a filter on material 1 with a\r\npercentage of 1% of the second mesh has the highest value compared to the filter,\r\nwhich is 9.8181 x10-2\r\n\r\nreactions/cm3\r\ns.\r\n\r\nKeywords: uranium, SCWR, neutron reaction rate, SRAC."^^<http://www.w3.org/2001/XMLSchema#string> .
<http://digilib.unila.ac.id/id/eprint/61833> <http://purl.org/dc/terms/date> "2021" .
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