@misc{eprints61833,
           title = {PERHITUNGAN LAJU REAKSI NEUTRON DALAM REAKTOR SCWR
(SUPERCRITICAL WATER REACTOR) MODEL PERANGKAT
(ASSEMBLY) HEKSAGONAL BERBAHAN BAKAR URANIUM},
          author = {1517041066 Sharen Herya Reafinola},
         address = {UNIVERSITAS LAMPUNG},
       publisher = {FAKULTAS MATEMATIKA DAN ILMU PENGETAHUAN ALAM},
            year = {2021},
             url = {http://digilib.unila.ac.id/61833/},
        abstract = {Telah dilakukan perhitungan laju reaksi fisi dan penangkapan neutron dengan
filter dan tanpa filter model geometri heksagonal menggunakan program SRAC
kode REACT. Penelitian ini menggunakkan bahan bakar uranium-235 dan
uranium-238. Hasil perhitungan Laju reaksi fisi pada material 1 dan material 3
dengan menggunakan filter dan tanpa filter meningkat seiring dengan
meningkatnya nilai persentase pengayaan U

235. Nilai tertinggi pada laju reaksi fisi
neutron material 1 tanpa filter terdapat pada mesh ke-2 dengan pengayaan 1\%
yaitu sebesar 3,0747x10-2

reaksi/cm3

s. Sedangkan laju reaksi penangkapan
neutron menggunakan filter meningkat seiring meningkatnya persentase pada U235
dengan pengayaan 1\% mesh ke-5 yaitu dengan nilai sebesar 9,8627 x10-2
reaksi/cm3

s. Kemudian Laju reaksi fisi neutron tanpa filter pada material 3

meningkat seiring dengan meningkatnya persentase pada pengayaan 1\% mesh ke-
5 yaitu sebesar 9,4778 x10-2

reaksi/cm3

s. Hal ini dikarenakan meningkatnya
persentase pada pengayaan U235 pada pin bahan bakar. Sedangkan laju reaksi

penangkapan menggunakan filter pada material 1 dengan persentase 1\% mesh ke-
2 memiliki nilai tertinggi dibandingkan dengan filter yaitu sebesar 9,8181 x10-2

reaksi/cm3
s.

Kata kunci : Uranium, SCWR, Laju Reaksi Neutron dan SRAC.
Calculation of the rate of fission and neutron capture reactions with a filter and
without a filter has been carried out using a hexagonal geometry model using the
REACT code SRAC program. This research uses uranium-235 and uranium-238
as fuel. Calculation results The rate of fission reaction in material 1 and material
3 using a filter and without a filter increases with the increase in the percentage
value of U235 enrichment. The highest value for the neutron fission reaction rate
of material 1 without a filter is found in the second mesh with 1\% enrichment,
which is 3.0747x10-2

reactions/cm3

s. Meanwhile, the rate of neutron capture
reaction using a filter increases with the increase in the percentage of U235 with
1\% enrichment of the 5th mesh, with a value of 9.8627 x10-2

reactions/cm3
s. Then
the unfiltered neutron fission reaction rate on material 3 increased along with the
increasing percentage in the 5th 1\% enrichment mesh, which was 9.4778 x10-2
reactions/cm3

s. This is due to the increasing percentage of U235 enrichment in
the fuel pin. While the rate of capture reaction using a filter on material 1 with a
percentage of 1\% of the second mesh has the highest value compared to the filter,
which is 9.8181 x10-2

reactions/cm3
s.

Keywords: uranium, SCWR, neutron reaction rate, SRAC.}
}