FUEL BURN-UP DISTRIBUTION AND TRANSURANIC NUCLIDE CONTENTS PRODUCED AT THE FIRST CYCLE OPERATION OF AP1000
DOI:
https://doi.org/10.17146/tdm.2016.18.2.2665Keywords:
Fuel Burn-Up, Transuranic, AP1000, EOC, SRAC2006Abstract
AP1000 reactor core was designed with nominal power of 1154 MWe (3415 MWth), operated within life time of 60 years and cycle length of 18 months. For the first cycle, the AP1000 core uses three kinds of UO2 enrichment, they are 2.35 w/o, 3.40 w/o and 4.45 w/o. Absorber materials such as ZrB2, Pyrex and Boron solution are used to compensate the excess reactivity at the beginning of cycle. In the core, U-235 fuels are burned by fission reaction and produce energy, fission products and new neutron. Because of the U-238 neutron absoption reaction, the high level radioactive waste of heavy nuclide transuranic such as Pu, Am, Cm and Np are also generated. They have a very long half life. The purpose of this study is to evaluate the result of fuel burn-up distribution and heavy nuclide transuranic contents produced by AP1000 at the end of first cycle operation (EOFC). Calculation of ¼ part of the AP1000 core in the 2 dimensional model has been done using SRAC2006 code with the module of COREBN/HIST. The input data called the table of macroscopic crossection, is calculated using module of PIJ. The result shows that the maximum fuel assembly (FA) burn-up is 27.04 GWD/MTU, that is still lower than allowed maximum burn-up of 62 GWD/MTU. Fuel loading position at the center/middle of the core will produce bigger burn-up and transuranic nuclide than one at the edges the of the core. The use of IFBA fuel just give a small effect to lessen the fuel burn-up and transuranic nuclide production.
References
Anonim. AP1000 Design Control Document Revision 18. Chapter 4.3 Nuclear Design. Available from ; http://www.nrc.gov/docs/ML1034/ML103480532.pdf. Accessed June, 2016.
D. Haas, D.J. Hamilton. Fuel cycle strategies and plutonium management in Europe. Progress in Nuclear Energy 2007; 49:574-582
https://doi.org/10.1016/j.pnucene.2007.09.001
Bo Cao, Jun Wu, Tongrui Yang, Xubo Ma and Yixue Chen. Preliminary Study on Nuclear Fuel Cycle Scenarios of China before 2050. Energy Procedia 2013; 39:294-299
https://doi.org/10.1016/j.egypro.2013.07.216
Heui-Joo Choi, Dongkeun Cho, Donghak Kook, Jongwon Choi. Current status of spent fuels and the development of computer programs for the PWR spent fuel management in Korea Progress in Nuclear Energy 2011; 53(3):290-297
https://doi.org/10.1016/j.pnucene.2010.12.006
Robbert J. Fetermen. AP1000 Core Design With 50% MOX Loading. Annals of Nuclear Energy 2009; 36:324-330
https://doi.org/10.1016/j.anucene.2008.11.022
Jeffrey R. Secker, Beard J. Johansen, David L. Stucker, Odelli Ozer, Kostadin Ivanov, Serkan Yilmaz, E.H. Young. Optimum Discharge Burnup and Cycle Length for PWRs. Nuclear Technology 2005; 151:109-119
https://doi.org/10.13182/NT05-A3636
R.F. Mahmoud, M. K. Shaat, M.E. Nagy, S.A. Agamy, A. A. Abdelrahman. Burn-up credit in criticality safety of PWR spent fuel. Nuclear Engineering and Design 2014; 280: 628-633
https://doi.org/10.1016/j.nucengdes.2014.09.001
Kyu-Tae Kim. Evolutionary developments of advanced PWR nuclear fuels and cladding materials. Nuclear Engineering and Design 2013; 263:59-69
https://doi.org/10.1016/j.nucengdes.2013.04.013
C.E. Velasquez, R.V. Sousa, A. Fortini, C. Pereira, A.L. Costa, C.A.M. da Silva, M.A.F. Veloso, A.H. de Oliveira, F.R. de Carvalho. Spent fuel criticality and compositions evaluation for long-term disposal in a generic cask. Nuclear Engineering and Design 2014; 275:168-178
https://doi.org/10.1016/j.nucengdes.2014.04.021
S. Rong-Jiun, L. Min-Hua, L. Jenq-Horng. Quantifying the effects of depletion parameters on the PWR spent fuel reactivity based on nuclide sensitivity coefficients. Annals of Nuclear Energy 2016; 87:126-136
https://doi.org/10.1016/j.anucene.2015.08.025
S.J. Rose, J.N. Wilson, N. Capellan, S. David, P. Guillemin, E. Ivanov, O. Méplan, A. Nuttin, S. Siem. Minimization of actinide waste by multi-recycling of thoriated fuels in the EPR reactor. Annals of Nuclear Energy 2011; 38:2619-2624
https://doi.org/10.1016/j.anucene.2011.06.029
Anis R., Mass Changes Analysis of Fissile And Non Fissile Materials in The PWR 1000 MWe Using ORIGEN-ARP 5.1. Journal of Nuclear Reactor Technology TRI DASA MEGA 2015; 17:13-18. (In Indonesian)
https://doi.org/10.17146/tdm.2015.17.1.2234
C.J. Diez, O. Buss, A. Hoefer, D. Porsch, O. Cabellos. Comparison of nuclear data uncertainty propagation methodologies for PWR burn-up simulations. Annals of Nuclear Energy 2015; 77:101-114.
https://doi.org/10.1016/j.anucene.2014.10.022
Keisuke Okumura, Teruhiko Kugo, Kunio Kaneko and Keichiro Tsuchihashi. SRAC2006; A Comprehensive Neutronics Calculation Code System. JAERI-Data/Code 2007-004, January 2007, Japan Atomic Energy Agency
Jati S., Iman K.. Validation of COREBN / HIST Computer Code for Fuel Burn-Up Calculations and Fuel Management of RSG - GAS Core. Jurnal of Nuclear Reactor Teknologi TRI DASA MEGA 2007; 9:119-131. (In Indonesian)
