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SETSCI - Volume 1 (2017)
ISMSIT2017 - International Symposium on Multidisciplinary Studies and Innovative Technologies, Tokat, Turkey, Dec 02, 2017

Time-Dependent Neutronic and Burn-up Analyses of in a Thorium-Based ADS cooled with Various Coolants
Gizem Bakır1*, Hüseyin Yapıcı2
1Cunhuriyet University, Sivas, Turkey
2Erciyes University, Kayseri, Turkey
* Corresponding author: gizem.bakir@hotmail.com
Published Date: 2017-12-08   |   Page (s): 60-64   |    5475     26
ABSTRACT This study presents the investigation of thorium utilization in an ADS with Lead-Bismuth Eutectic (LBE) target. To effectively burn thorium, the ThO2 fuel rods cylindrically prepared, and cladded with SiC, are mixed with 233UO2 at volumetric ratio of 1%. These fuel rods are placed in the fuel zone in hexagonal arrangement. Three different coolant cases, helium (He) gas, light water (H2O) and heavy water (D2O), are individually examined for cooling of fuel zone. The volumetric percentages of fuel, clad and coolant are 60%, 10% and 30%, respectively. The LBE-target is bombarded by protons amplified to 1000 MeV in linear accelerator (LINAC) which in turn releases 29-30 high-energetic neutrons per proton via the spallation reactions. Proton beam power is assumed as 20 MW corresponding to 1.24828·1017 protons per second. The steady-state neutronic and subsequent time-dependent burn calculations are performed by using MCNPX 2.7 with LA150 library and CINDER computer codes, respectively. The ADSs can be operated under subcritical mode until the value of keff increases to 0.980-0.985. Subject to this constraint of keff, the maximum operation times are determined as 184, 825 and 2215 days and at end of these times, the values of gain (G) increase up to 17.362, 12.909 and 9.100, in the cases of H2O, D2O and He coolants, respectively.  
KEYWORDS Thorium utilization; Accelerator Driven System; Fissile breeding; Fuel enrichment
REFERENCES [1 ] Rubbia C. et al., "Conceptual Design of a Fast Neutron Operated High Power Energy Amplifier", CERN/AT/95-44 (ET), Sept. 29, 1995.

[2 ] Rubbia C., “A future for thorium power?”, in Proceedings of the ThEC13 Conference, Oct. 27-31, 2013.

[3 ] Thanh Mai Vu, Takanori Kitada, Transmutation Strategy Using Thorium-Reprocessed Fuel ADS for Future Reactors in Vietnam, Science and Technology
of Nuclear Installations, Volume 2013, Article ID 674638, 5 pages.

[4 ] Thanh Mai Vu, Takanori Kitada, Seed and blanket thorium-reprocessed fuel ADS: Multi-cycle approach for higher thorium utilization and TRU transmutation, Annals of Nuclear Energy 75 (2015) 438–442.

[5 ] Graiciany de Paula Barros, Claubia Pereira, Maria A. F. Veloso, and Antonella L. Costa, Study of an ADS Loaded with Thorium and Reprocessed Fuel, Science
and Technology of Nuclear Installations, Volume 2012, Article ID 934105, 12 pages.

[6 ] G.P. Barros, C. Pereira, M.A.F. Veloso, A.L. Costa, Thorium and reprocessed fuel utilization in an accelerator-driven system, Annals of Nuclear Energy 80 (2015) 14–20.

[7 ] Graiciany P. Barros, Carlos E. Velasquez, Claubia Pereira, Maria Auxiliadora F. Veloso, Antonella L. Costa, Depletion evaluation of an ADS using reprocessed fuel International Journal of Hydrogen Energy 40 (2015) 15148-15152.

[8 ] Ali Pazirandeh, Laia Shirmohammadi, Simulation of an Accelerator Driven Subcritical Core with Mixed Uranium-Thorium Fuel, World Journal of Engineering and Technology, 2015, 3, 328-333.

[9 ] Yapıcı, H., Genç, G., Demir, N., Neutronic limits in infinite target mediums driven by high energetic protons. Annals of Nuclear Energy, 2007, 34, 374–384.

[10 ] G. Bakır, G. Genç, H. Yapıcı, Study of a Conceptual Accelerator Driven System Loaded with Thorium Dioxide Mixed with Transuranic Dioxides in TRISO Particles, Nuclear Technology & Radiation Protection, 2016, 31, 197-206.

[11 ] G. Bakır, S. B. Selçuklu, G. Genç, H. Yapıcı, Neutronic Analysis of LBE-Uranium Spallation Target Accelerator Driven System Loaded with Uranium Dioxide in TRISO Particles, Acta Physica Polonica A, 2016, 130, 30-32.

[12 ] G. Bakır, G. Genç, H. Yapıcı, Time-Dependent Neutronic Analysis of a Power-Flattened Gas Cooled Accelerator Driven System Fuelled with Thorium, Uranium, Plutonium, and Curium Dioxides TRISO Particles, Science and Technology of Nuclear Installations, 2016, 2016, 11.

[13 ] Pelowitz, D.B., MCNPX User’s Manual, Version 2.7.0, LA-CP-11-00438, Los Alamos Scientific Laboratory (2011).

[14 ] Chadwick, M.B., Young, P.G., Chiba, S., Frankle, S.C., Hale, G.M., Hughes, H.G., Koning, A. J., Little, R.C., MacFarlane, R.E., Prael, R.E., Waters, L.S., 1999. Cross-section Evaluations to 150 MeV for Accelerator-driven Systems and Implementation in MCNPX. Nuclear Science and Engineering, 131, 293.

[15 ] WilsonW.B., et al., Manual for CINDER’90 Version 07.4 Codes and Data, LA-UR-07-8412, Los Alamos Scientific Laboratory 2007, Version 07.4.2, updated (March 2008).

[16 ] Yapıcı H., CBURN interface computer code for evaluation of time-dependent CINDER90 outputs, 2017, Erciyes University, Turkey.


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