Calculation of fuel burnup and radionuclide inventory for the HEU and potential LEU fuels in the IRT research reactor

Calculation of fuel burnup and radionuclide inventory for the HEU and potential LEU fuels in the IRT research reactor

The study of core conversion of the IRT research reactor from the HEU to LEU fuels has been conducted in this paper. Fuel burnup, buildup of actinides and fission product inventory for the IRT research reactor with UO2-Al dispersion fuel for the various different uranium enrichments and the uranium...

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Main Authors: Saadou Aldawahrah, S. Dawahra, K. Khattab, G. Saba, M. Boush
Format: Article
Language:English
Published: Elsevier 2018-12-01
Series:Results in Physics
Online Access:http://www.sciencedirect.com/science/article/pii/S2211379718316243
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spelling doaj-8245fe9496a44136aa0f5bc05282b0c72020-11-24T23:26:36ZengElsevierResults in Physics2211-37972018-12-0111564569Calculation of fuel burnup and radionuclide inventory for the HEU and potential LEU fuels in the IRT research reactorSaadou Aldawahrah0S. Dawahra1K. Khattab2G. Saba3M. Boush4Corresponding author.; Nuclear Engineering Department, Atomic Energy Commission, P.O. Box 6091, Damascus, SyriaNuclear Engineering Department, Atomic Energy Commission, P.O. Box 6091, Damascus, SyriaNuclear Engineering Department, Atomic Energy Commission, P.O. Box 6091, Damascus, SyriaNuclear Engineering Department, Atomic Energy Commission, P.O. Box 6091, Damascus, SyriaNuclear Engineering Department, Atomic Energy Commission, P.O. Box 6091, Damascus, SyriaThe study of core conversion of the IRT research reactor from the HEU to LEU fuels has been conducted in this paper. Fuel burnup, buildup of actinides and fission product inventory for the IRT research reactor with UO2-Al dispersion fuel for the various different uranium enrichments and the uranium density such as: (IRT-3M 90% 1.1 g/cm3, IRT-3M 36% 2.51 g/cm3, IRT-4M 19.75% 3.25 g/cm3, IRT-4M 19.75% 3.48 g/cm3, IRT-4M 19.75% 3.71 g/cm3) have been carried out using the GETERA code. The multiplication factor (keff) of the IRT-3M and IRT-4M reactors were calculated using the MCNP4C code. The results showed, after 200 days of the reactor operation time that the total consumptions of 235U for the five cases were 73.85, 73.13, 72.66, 72.80 and 73.21 g respectively. The amounts of 239Pu produced in the core were: 0.43, 3.39, 5.90, 6.13 and 6.35 g respectively. The total radioactivities of fuel assembly were: 2.78E+15, 2.83E+15, 2.86E+15, 2.88E+15 and 2.89E+15 Bq respectively. Finally, from the neutronic view point, the LEU fuel was validated to be a suitable candidate for the fuel conversion of the IRT in the future. Keywords: Burnup, IRT reactor, HEU, LEU, GETERA code, Fission productshttp://www.sciencedirect.com/science/article/pii/S2211379718316243
collection DOAJ
language English
format Article
sources DOAJ
author Saadou Aldawahrah
S. Dawahra
K. Khattab
G. Saba
M. Boush
spellingShingle Saadou Aldawahrah
S. Dawahra
K. Khattab
G. Saba
M. Boush
Calculation of fuel burnup and radionuclide inventory for the HEU and potential LEU fuels in the IRT research reactor
Results in Physics
author_facet Saadou Aldawahrah
S. Dawahra
K. Khattab
G. Saba
M. Boush
author_sort Saadou Aldawahrah
title Calculation of fuel burnup and radionuclide inventory for the HEU and potential LEU fuels in the IRT research reactor
title_short Calculation of fuel burnup and radionuclide inventory for the HEU and potential LEU fuels in the IRT research reactor
title_full Calculation of fuel burnup and radionuclide inventory for the HEU and potential LEU fuels in the IRT research reactor
title_fullStr Calculation of fuel burnup and radionuclide inventory for the HEU and potential LEU fuels in the IRT research reactor
title_full_unstemmed Calculation of fuel burnup and radionuclide inventory for the HEU and potential LEU fuels in the IRT research reactor
title_sort calculation of fuel burnup and radionuclide inventory for the heu and potential leu fuels in the irt research reactor
publisher Elsevier
series Results in Physics
issn 2211-3797
publishDate 2018-12-01
description The study of core conversion of the IRT research reactor from the HEU to LEU fuels has been conducted in this paper. Fuel burnup, buildup of actinides and fission product inventory for the IRT research reactor with UO2-Al dispersion fuel for the various different uranium enrichments and the uranium density such as: (IRT-3M 90% 1.1 g/cm3, IRT-3M 36% 2.51 g/cm3, IRT-4M 19.75% 3.25 g/cm3, IRT-4M 19.75% 3.48 g/cm3, IRT-4M 19.75% 3.71 g/cm3) have been carried out using the GETERA code. The multiplication factor (keff) of the IRT-3M and IRT-4M reactors were calculated using the MCNP4C code. The results showed, after 200 days of the reactor operation time that the total consumptions of 235U for the five cases were 73.85, 73.13, 72.66, 72.80 and 73.21 g respectively. The amounts of 239Pu produced in the core were: 0.43, 3.39, 5.90, 6.13 and 6.35 g respectively. The total radioactivities of fuel assembly were: 2.78E+15, 2.83E+15, 2.86E+15, 2.88E+15 and 2.89E+15 Bq respectively. Finally, from the neutronic view point, the LEU fuel was validated to be a suitable candidate for the fuel conversion of the IRT in the future. Keywords: Burnup, IRT reactor, HEU, LEU, GETERA code, Fission products
url http://www.sciencedirect.com/science/article/pii/S2211379718316243
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