PROSPECT OF URANIUM NITRIDE FOR PRESSURIZED WATER REACTOR (PWR)
A small Pressurized Water Reactors (PWRs) core loaded with uranium <br /> <br /> <br /> <br /> <br /> nitride fuel (UN) and mixed nitride fuel (UN-PuN), Pa-231 as a material burnable <br /> <br /> <br /> <br /> <br /> poison, an...
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id-itb.:192362017-09-27T14:41:02ZPROSPECT OF URANIUM NITRIDE FOR PRESSURIZED WATER REACTOR (PWR) DEWI SYARIFAH (NIM :20211003) ; Pembimbing Prof. Dr. Eng. Zaki Su'ud, RATNA Indonesia Theses INSTITUT TEKNOLOGI BANDUNG https://digilib.itb.ac.id/gdl/view/19236 A small Pressurized Water Reactors (PWRs) core loaded with uranium <br /> <br /> <br /> <br /> <br /> nitride fuel (UN) and mixed nitride fuel (UN-PuN), Pa-231 as a material burnable <br /> <br /> <br /> <br /> <br /> poison, and Americium as a addition of minor actinide has been performed. Pa- <br /> <br /> <br /> <br /> <br /> 231 known as actinide material, have large capture cross section and capability to <br /> <br /> <br /> <br /> <br /> convert into fissile material that can decrease excess reactivity. Americium is one <br /> <br /> <br /> <br /> <br /> of minor actinide which have long half life. The objective of adding americium is <br /> <br /> <br /> <br /> <br /> to decrease nuclear spent fuel in the world. The neutronic analysis results of <br /> <br /> <br /> <br /> <br /> infinite cell calculation shows that mixed nitride fuel have k-inf greater than <br /> <br /> <br /> <br /> <br /> uranium nitride fuel. It caused by the addition of Pu-239 in mixed nitride fuel. In <br /> <br /> <br /> <br /> <br /> fuel fraction analysis, the optimum fuel fraction are 50% fuel fraction, 20% <br /> <br /> <br /> <br /> <br /> cladding and 30% moderator. For the addition of Pa-231 and Americium, the <br /> <br /> <br /> <br /> <br /> lowest excess reactivity for UN when enrichment U-235 9%, Pa-231 1% and Am <br /> <br /> <br /> <br /> <br /> 1%, the excess reactivity is 7,5%. And for mix nitride fuel, when enrichment U- <br /> <br /> <br /> <br /> <br /> 235 1%, Pa-231 20% and Am 12%, the excess reactivity is 3,7%. In core <br /> <br /> <br /> <br /> <br /> configuration, it's better to use heterogeneous than homogeneous core <br /> <br /> <br /> <br /> <br /> configuration, because the radial power distribution is flatter. text |
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A small Pressurized Water Reactors (PWRs) core loaded with uranium <br />
<br />
<br />
<br />
<br />
nitride fuel (UN) and mixed nitride fuel (UN-PuN), Pa-231 as a material burnable <br />
<br />
<br />
<br />
<br />
poison, and Americium as a addition of minor actinide has been performed. Pa- <br />
<br />
<br />
<br />
<br />
231 known as actinide material, have large capture cross section and capability to <br />
<br />
<br />
<br />
<br />
convert into fissile material that can decrease excess reactivity. Americium is one <br />
<br />
<br />
<br />
<br />
of minor actinide which have long half life. The objective of adding americium is <br />
<br />
<br />
<br />
<br />
to decrease nuclear spent fuel in the world. The neutronic analysis results of <br />
<br />
<br />
<br />
<br />
infinite cell calculation shows that mixed nitride fuel have k-inf greater than <br />
<br />
<br />
<br />
<br />
uranium nitride fuel. It caused by the addition of Pu-239 in mixed nitride fuel. In <br />
<br />
<br />
<br />
<br />
fuel fraction analysis, the optimum fuel fraction are 50% fuel fraction, 20% <br />
<br />
<br />
<br />
<br />
cladding and 30% moderator. For the addition of Pa-231 and Americium, the <br />
<br />
<br />
<br />
<br />
lowest excess reactivity for UN when enrichment U-235 9%, Pa-231 1% and Am <br />
<br />
<br />
<br />
<br />
1%, the excess reactivity is 7,5%. And for mix nitride fuel, when enrichment U- <br />
<br />
<br />
<br />
<br />
235 1%, Pa-231 20% and Am 12%, the excess reactivity is 3,7%. In core <br />
<br />
<br />
<br />
<br />
configuration, it's better to use heterogeneous than homogeneous core <br />
<br />
<br />
<br />
<br />
configuration, because the radial power distribution is flatter. |
format |
Theses |
author |
DEWI SYARIFAH (NIM :20211003) ; Pembimbing Prof. Dr. Eng. Zaki Su'ud, RATNA |
spellingShingle |
DEWI SYARIFAH (NIM :20211003) ; Pembimbing Prof. Dr. Eng. Zaki Su'ud, RATNA PROSPECT OF URANIUM NITRIDE FOR PRESSURIZED WATER REACTOR (PWR) |
author_facet |
DEWI SYARIFAH (NIM :20211003) ; Pembimbing Prof. Dr. Eng. Zaki Su'ud, RATNA |
author_sort |
DEWI SYARIFAH (NIM :20211003) ; Pembimbing Prof. Dr. Eng. Zaki Su'ud, RATNA |
title |
PROSPECT OF URANIUM NITRIDE FOR PRESSURIZED WATER REACTOR (PWR) |
title_short |
PROSPECT OF URANIUM NITRIDE FOR PRESSURIZED WATER REACTOR (PWR) |
title_full |
PROSPECT OF URANIUM NITRIDE FOR PRESSURIZED WATER REACTOR (PWR) |
title_fullStr |
PROSPECT OF URANIUM NITRIDE FOR PRESSURIZED WATER REACTOR (PWR) |
title_full_unstemmed |
PROSPECT OF URANIUM NITRIDE FOR PRESSURIZED WATER REACTOR (PWR) |
title_sort |
prospect of uranium nitride for pressurized water reactor (pwr) |
url |
https://digilib.itb.ac.id/gdl/view/19236 |
_version_ |
1821119778184495104 |