Desain Study of Pb-Bi Cooled Fast Reactors with Natural Uranium as Fuel Cycle Input Using Special Shuffling Strategy in Radial Direction

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Design study of Pb-Bi cooled fast reactors with natural uranium as fuel cycle input using special radial shuffling strategy has been performed. The reactors utilizes UN-PUN as fuel, Eutectic Pb-Bi as coolant, and can be operated without refueling for 10 years in each batch. Reactor design optimization is performed to utilize natural uranium as fuel cycle input. This reactor subdivided into 6 regions with equal volume in radial directions. The natural uranium is initially put in region 1, and after one cycle of 10 years of burn-up it is shifted to region 2 and the region 1 is filled by fresh natural uranium fuel. This concept is basically applied to all regions. The calculation has been done by using SRAC-Citation system code and JENDL-3.2 library. The effective multiplication factor change increases monotonously during 10 years reactor operation time. There is significant power distribution change in the central part of the core during the BOC and the EOC. It is larger than that in the case of modified CANDLE case which use axial direction burning region move. The burnup level of fuel is slowly grows during the first 15 years but then grow fastly in the rest of burnup history. This pattern is a little bit different from the case of modified CANDLE burnup scheme in Axial direction in which the slow growing burnup period is relatively longer almost half of the burnup history.

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530-535

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September 2013

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© 2013 Trans Tech Publications Ltd. All Rights Reserved

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[1] Z. Su'ud and H. Sekimoto, The Prospect of Gas Cooled Fast Reactors for Long Life Reactors with Natural Uranium as Fuel Cycle Input, Annals of Nuclear Energy, Vol. 54 (2013), p.58–66.

DOI: 10.1016/j.anucene.2012.09.014

Google Scholar

[2] Zaki Su'ud, Bakrie Arbie, and Sedyartomo S.: The Prospect of MOX Fuel Based Pb-BiCooled Small Nuclear Power Reactors, Progress of Nuclear Energy, Vol. 47 (2005), h. 212-221.

DOI: 10.1016/j.pnucene.2005.05.021

Google Scholar

[3] Zaki Su'ud, Neutronic Performance Comparation of MOX, Nitride and Metallic fuel based 25-100 MWe Pb-Bi Cooled Long Life Fast Reactors without on site Refuelling, Progress ofNuclear Energy, Vol. 50 (2008), pp.276-278.

DOI: 10.1016/j.pnucene.2007.11.009

Google Scholar

[4] Epung S.B. et al. (2008) Reactor Core Design Optimization Of The 200 MWt Pb-Bi Cooled Fast Reactor for Hydrogen Production, Progress of Nuclear Energy, Vol. 50, pp.434-437.

DOI: 10.1016/j.pnucene.2007.11.027

Google Scholar

[5] Zaki Su'ud: Comparative Study on Safety Performance of Nitride Fueled Lead-Bismuth CooledFast Reactor with Various Power Level", Progress in Nuclear Energy Vol. 32 no. 3-4 (1998), pp.571-577.

DOI: 10.1016/s0149-1970(97)00045-0

Google Scholar

[6] IAEA TECDOC 1536 Satus of Small Reactors Without On-site Refueling, 2007, 739-759.

Google Scholar

[7] Zaki Su'ud, Safety Performance Comparation of MOX, Nitride and Metallic fuel based 25-100MWe Pb-Bi Cooled Long Life Fast Reactors without on site Refuelling, Progress of Nuclear Energy, Vol. 50 (2008), pp.157-162.

DOI: 10.1016/j.pnucene.2007.10.028

Google Scholar

[8] Zaki Su'ud and H. Sekimoto: A concept of Long-life Small Safe Reactor, SR/TIT '91: International Specialist Meeting on Potentials of Small Nuclear Reactors for Future Clean and Safe Energy Resources, TIT- Tokyo, Elsevier, (1992).

Google Scholar

[9] H. Sekimoto and Zaki S. , Design Study of Lead and Lead-bismuth Cooled Small Long-life Nuclear Power Reactors Using Metallic and Nitride Fuel, Nuclear Technology, Vol. 105, no. 3 (1995), pp.307-313.

DOI: 10.13182/nt109-307

Google Scholar

[10] Zaki Su'ud and H. Sekimoto : Design and Safety Aspect of Lead and Lead Bismuth Cooled Long-Life Small-safe Fast Reactor for Various Core Configuration, Journal of Nuclear Science and Technology Vol. 32 no. 9 (1995), pp.834-845.

DOI: 10.1080/18811248.1995.9731785

Google Scholar

[11] Su'ud, Z. and H. Sekimoto, Preliminary Design Study of the Ultra Long Life Fast Reactor', Nuclear Engineering and Design, Vol. 140, 1993, pp.251-260.

DOI: 10.1016/0029-5493(93)90079-o

Google Scholar

[12] Su'ud, Z. and H. Sekimoto, Design and Safety Aspect of Lead and Lead Bismuth Cooled Long-Life Small-safe Fast Reactor for Various Core Configuration, 1995, Journal of Nuclear Science and Technology 32 (9), pp.834-845.

DOI: 10.1080/18811248.1995.9731785

Google Scholar

[13] Sekimoto, H. et al. (2001) CANDLE: The New Burn-up Strategy, Nuclear Science and Engineering, 139, pp.1-12.

Google Scholar

[14] Sekimoto, H. and S. Miyashita (2005) Startup of CANDLE Burnup in Fast Reactor from Enriched Uranium Core, Proc. of 12th Conf. on Emerging Nuclear Energy System (ICENES 2005), Aug. 21-26, 2005, SCK. CEN, Mol., Brussels, Belgium.

DOI: 10.1016/j.enconman.2006.02.007

Google Scholar

[15] Rida SNM and Z. Su'ud (2009) Design Study of Pb-Bi Cooled Fast Reactors Which Fuel Cycle Input is Natural Uranium, International Journal of Nuclear Energy Science and Technology Vol. 4 No. 3, pp.217-222.

DOI: 10.1504/ijnest.2009.027042

Google Scholar

[16] Keisuke OKUMURA, Teruhiko KUGO, Kunio KANEKO and Keichiro TSUCHIHASHI, SRAC (Ver. 2002) ; The comprehensive neutronics calculation code system, JAERI Report, (2002).

Google Scholar

[17] Nakagawa, M. and Tsuchihashi, K. , SLAROM: A Code for Cell Homogenization Clculation of Fast Reactor, JAERI M 1294, (1984).

Google Scholar

[18] Z. Su'ud, FI-ITB CH1 code manual, internal report.

Google Scholar