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Numerical Computation of Fission-Product Poisoning Build-up and Burn-up Rate in a Finite Cylindrical Nuclear Reactor Core

Mathew Ademola Jayeola [1] , Musbaudeen Kewulere Fasasi [2] , Adebimpe Amos Amosun [3] , Ayodeji Olalekan Salau [4] , Babatunde Michael Ojo [5]

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All fission products are classified as reactor poisons because they absorb neutrons to some extent, most of which buildup slowly as the fuel burns up and eventually constitutes a long term reactivity effect in the core. Amidst the numerous fission fragments produced per fission, the presence of Xenon-135 and Samarium-149 has the greatest effect on a reactor core multiplication factor because of their large absorption cross-sections. In this study, we present a modified one-group time independent neutron diffusion equation using the method of Eigen functions and also provided an algorithm to calculate the temperature variations of the neutron fluxes. The solution obtained from the diffusion equation was used to determine the initial thermal neutron flux needed for the reactor startup. The four basic fission-product poisoning buildup and burn-up rate equations were solved using direct integration method and constant flux approximation over a particular time interval. Furthermore, a computer algorithm called Java code for Fission-Product Poisioning Build-up and Burn-up (Jac-FPPB) code was designed to calculate the temperature variations of the neutron fluxes, fission -isotopes cross sections and the atom concentrations of the fission products over a given time interval. The result from Jac-FPPB code showed that the neutron fluxes and neutron energies increase as the temperature of the fuel increases. In addition, the computed atom concentrations of each fission isotopes at any given time interval showed that the isotopes increasingly build up steadily at the initial time interval and rises to a constant level where the buildup rate of the isotopes approximately equals its burn up rate. This study concluded that the designed algorithm (JaC-FPBB code) proved efficient as it could compute the build-up and burn-up rates for the two important fission fragments in a nuclear reactor core. The code is easily accessible and could serve as a tool for the development of nuclear energy in developing countries, especially Nigeria.

Numerical computation, Cylindrical reactor core, Fission-Products poisoning, Neutron diffusion equation, Samarium-149, Xenon-135
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Birincil Dil en Mühendislik, Ortak Disiplinler Araştırma Makaleleri Yazar: Mathew Ademola Jayeola (Sorumlu Yazar)Kurum: Department of Physics and Engineering Physics, Faculty of Science, Obafemi Awolowo UniversityÜlke: Nigeria Yazar: Musbaudeen Kewulere Fasasi (Sorumlu Yazar)Kurum: Center for Energy Research and Development, Obafemi Awolowo University, Ile-Ife, NigeriaÜlke: Nigeria Yazar: Adebimpe Amos Amosun (Sorumlu Yazar)Kurum: Department of Physics and Engineering Physics, Faculty of Science, Obafemi Awolowo University.Ülke: Nigeria Orcid: 0000-0002-6264-9783Yazar: Ayodeji Olalekan Salau (Sorumlu Yazar)Kurum: Department of Electronic and Electrical Engineering, Obafemi Awolowo University, Faculty of Technology, Ile-Ife, Nigeria.Ülke: Nigeria Yazar: Babatunde Michael Ojo (Sorumlu Yazar)Kurum: Department of Physics and Engineering Physics, Faculty of Science, Obafemi Awolowo University.Ülke: Nigeria
 Bibtex @araştırma makalesi { bilgesci397197, journal = {Bilge International Journal of Science and Technology Research}, issn = {2651-401X}, eissn = {2651-4028}, address = {Kutbilge Akademisyenler Derneği}, year = {2018}, volume = {2}, pages = {17 - 30}, doi = {10.30516/bilgesci.397197}, title = {Numerical Computation of Fission-Product Poisoning Build-up and Burn-up Rate in a Finite Cylindrical Nuclear Reactor Core}, key = {cite}, author = {Fasasi, Musbaudeen Kewulere and Jayeola, Mathew Ademola and Ojo, Babatunde Michael and Salau, Ayodeji Olalekan and Amosun, Adebimpe Amos} } APA Jayeola, M , Fasasi, M , Amosun, A , Salau, A , Ojo, B . (2018). Numerical Computation of Fission-Product Poisoning Build-up and Burn-up Rate in a Finite Cylindrical Nuclear Reactor Core. Bilge International Journal of Science and Technology Research, 2 (1), 17-30. DOI: 10.30516/bilgesci.397197 MLA Jayeola, M , Fasasi, M , Amosun, A , Salau, A , Ojo, B . "Numerical Computation of Fission-Product Poisoning Build-up and Burn-up Rate in a Finite Cylindrical Nuclear Reactor Core". Bilge International Journal of Science and Technology Research 2 (2018): 17-30 Chicago Jayeola, M , Fasasi, M , Amosun, A , Salau, A , Ojo, B . "Numerical Computation of Fission-Product Poisoning Build-up and Burn-up Rate in a Finite Cylindrical Nuclear Reactor Core". Bilge International Journal of Science and Technology Research 2 (2018): 17-30 RIS TY - JOUR T1 - Numerical Computation of Fission-Product Poisoning Build-up and Burn-up Rate in a Finite Cylindrical Nuclear Reactor Core AU - Mathew Ademola Jayeola , Musbaudeen Kewulere Fasasi , Adebimpe Amos Amosun , Ayodeji Olalekan Salau , Babatunde Michael Ojo Y1 - 2018 PY - 2018 N1 - doi: 10.30516/bilgesci.397197 DO - 10.30516/bilgesci.397197 T2 - Bilge International Journal of Science and Technology Research JF - Journal JO - JOR SP - 17 EP - 30 VL - 2 IS - 1 SN - 2651-401X-2651-4028 M3 - doi: 10.30516/bilgesci.397197 UR - http://dx.doi.org/10.30516/bilgesci.397197 Y2 - 2018 ER - EndNote %0 Bilge International Journal of Science and Technology Research Numerical Computation of Fission-Product Poisoning Build-up and Burn-up Rate in a Finite Cylindrical Nuclear Reactor Core %A Mathew Ademola Jayeola , Musbaudeen Kewulere Fasasi , Adebimpe Amos Amosun , Ayodeji Olalekan Salau , Babatunde Michael Ojo %T Numerical Computation of Fission-Product Poisoning Build-up and Burn-up Rate in a Finite Cylindrical Nuclear Reactor Core %D 2018 %J Bilge International Journal of Science and Technology Research %P 2651-401X-2651-4028 %V 2 %N 1 %R doi: 10.30516/bilgesci.397197 %U 10.30516/bilgesci.397197 ISNAD Jayeola, Mathew Ademola , Fasasi, Musbaudeen Kewulere , Amosun, Adebimpe Amos , Salau, Ayodeji Olalekan , Ojo, Babatunde Michael . "Numerical Computation of Fission-Product Poisoning Build-up and Burn-up Rate in a Finite Cylindrical Nuclear Reactor Core". Bilge International Journal of Science and Technology Research 2 / 1 (Mart 2018): 17-30. http://dx.doi.org/10.30516/bilgesci.397197