Analysis On The Change In Neutronic Parameters Due To Mispositioning Of Fuel In The Ap1000 Core
Abstract
AP1000 on the first cycle operation uses three types of UO2 fuel enrichments that are 2.35 w/o, 3.40 w/o and 4.50 w/o. To compensate excess reactivity, AP1000 uses an Integrated Fuel Burnable Absorber (IFBA) and a PYREX absorber as additional compensator to the boric solution in the moderator. IFBA is a burnable absorber made from ZrB2 which is integrated into the UO2 fuel. Human errors, such as fuel misposition, could happen when operators load fuel assemblies into the reactor core. For evaluating the design performance of AP1000, analysis on the change of neutronic parameters due to this fuel mispositioning need to be done. Analysis was performed on the reactor at hot zero power condition (HZP), beginning of cycle (BOC), and zero xenon condition with several cases of mispositioning between two adjacent fuels. Neutronic parameters, mainly the k-eff and power factor distribution will be derived from SRAC2006 computer code module of CITATION. One of the inputs required is fuel lattice macroscopic cross-section data, which are generated by PIJ module. These calculations performed condensation energy group of 107 into 10 groups with JENDL - 3.3 library cross section data. From the analysis, it can be concluded that misposition of the fuel in the first cycle of AP1000 core will result in very small change to the neutronic parameters. This very small change can not reduce the performance of the core.
References
[ 1] Balendra Sutharshan, Meena Mutyala, Ronald P Vijuk and Alok Mishra, “Asian Nuclear Prospects 2010-The AP1000TM Reactor: Passive Safety and Modular Design-“, Journal of Energy Procedia 00 (2010) 000-000.
[2] W. E. Cummins, M.M. Corletti, T. L. Schulz, “Westinghouse AP1000 Advanced Passive Plant”, Proceedings of ICAPP ’03, Cordoba, Spain, May 4-7, 2003, Paper 3235
[3] Jati Susilo and Rokhmadi, “Analysis of Criticallity Parameter of AP1000 Reactor Core Using SRAC-CITATION”, Prosidings of Scientific Meeting and Presentation on Basic Research and of Nuclear Science and Technology, Yogyakarta, 24-25 September 2013, pp. 94-102
[4] T. M. Sembiring and S. Pinem, “Evaluation of Moderator Temperature Coefficient of Reactivity for The 1000 MW PWR Nuclear Plant”, Prosidings of National Seminar 17th Technology And Safety of NPP and Nuclear Facility, Yogyakarta, October 1st, 2011, pp.164-174
[5] Jati Susilo and Lily Suparlina, “Analysis of Kinetic Parameter As a Function of Burn up of the AP1000 Core”, Prosidings of National Seminar 19th Technology And Safety of NPP and Nuclear Facility, Yogyakarta, September 24-25, 2013, pp.13-23
[6] Tagor Malem Sembiring and Surian Pinem, ”Evaluasi of Delayed Neutron Parameter of AP1000 Reactor”, Prosidings of National Seminar 18th Technology And Safety of NPP and Nuclear Facility, September 29, 2012, pp. 67-75
[7] Tukiran Surbakti, “Optimization of MOX Fuel for Core Design of AP1000 Reactor”, Prosidings of National Seminar 19th Technology And Safety of NPP and Nuclear Facility, Yogyakarta, September 24-25, 2013, pp. 23-34
[8] Rokhmadi, “Analisys of Control Rod Reactivity on The PWR AP1000 Design Fueled MOX”, Prosidings of National Seminar 19th Technology And Safety of NPP and Nuclear Facility, Yogyakarta, September 24-25, 2013, pp.34-45
[9] Tukiran Surbakti , “Evaluation of Kinetic Parameter for The Safety of The AP1000 Core Used MOX Fuel”, Prosidings of National Seminar 20th Technology And Safety of NPP and Nuclear Facility, Pontianak, June 19, 2014, pp.859-868
[10] Anonim, “AP1000 Design Control Document Chapter 4”, from:http://www.nrc.gov/ reactors/new-reactors/design-cert/ap1000/dcd/Tier%202/Chapter%204/4-1_r14.pdf, January 20, 2012
[11] T. L. Schulz, “Westinghouse AP1000 advanced passive plant”, Journal of Nuclear Engineering and Design 236 (2006), pp. 1547–1557.
[12] Keisuke Okumura, Teruhiko Kugo, Kunio Kaneko and Keichiro Tsuchihashi, “SRAC2006; A Comprehensive Neutronics Calculation Code System”, JAERI-Data/Code 2007-004, Japan Atomic Energy Agency, January 2007
[13] Jati Susilo, ” Verification of MVP-II and SRAC06 Code for the Case VERA Benchmark Reactor Core”, Journal TDM Vol.16, No.2, June 2014, ISSN 1411-240X, No. Acreditation: 402/AU2/ P2MI-LIPI/04/2012, pp.75-88