Optimization of Small Long Life Gas Cooled Fast Reactors with Natural Uranium as Fuel Cycle Input

Ariani, Menik; Su'ud, Z.; Monado, Fiber; Waris, A.; Khairurrijal,; Arif, I.; Ferhat, A.; Sekimoto, H.

doi:10.4028/www.scientific.net/AMM.260-261.307

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HomeApplied Mechanics and MaterialsEnergy, Environment and Sustainable DevelopmentOptimization of Small Long Life Gas Cooled Fast...

Optimization of Small Long Life Gas Cooled Fast Reactors with Natural Uranium as Fuel Cycle Input

Abstract:

In this study gas cooled reactor system are combined with modified CANDLE burn-up scheme to create small long life fast reactors with natural circulation as fuel cycle input. Such system can utilize natural Uranium resources efficiently without the necessity of enrichment plant or reprocessing plant. Therefore using this type of nuclear power plants optimum nuclear energy utilization including in developing countries can be easily conducted without the problem of nuclear proliferation. In this paper, optimization of Small and Medium Long-life Gas Cooled Fast Reactors with Natural Uranium as Fuel Cycle Input has been performed. The optimization processes include adjustment of fuel region movement scheme, volume fraction adjustment, core dimension, etc. Due to the limitation of thermal hydraulic aspects, the average power density of the proposed design is selected about 75 W/cc. With such condition we investigated small and medium sized cores from 300 MWt to 600 MWt with all being operated for 10 years without refueling and fuel shuffling and just need natural Uranium as fuel cycle input. The average discharge burn-up is about in the range of 23-30% HM.

Info:

Periodical:

Applied Mechanics and Materials (Volumes 260-261)

Main Theme:

Energy, Environment and Sustainable Development

Edited by:

Chang Tianharry

Pages:

307-311

DOI:

https://doi.org/10.4028/www.scientific.net/AMM.260-261.307

Citation:

M. Ariani et al., "Optimization of Small Long Life Gas Cooled Fast Reactors with Natural Uranium as Fuel Cycle Input", Applied Mechanics and Materials, Vols. 260-261, pp. 307-311, 2013

Online since:

December 2012

Authors:

Menik Ariani, Z. Su'ud, Fiber Monado, A. Waris, Khairurrijal, I. Arif, A. Ferhat, H. Sekimoto

Keywords:

Burn-Up History, Fuel Cycle Input, Fuel Shuffling, Long Life Operation, Modified CANDLE

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References

[1] Z. Su'ud and H. Sekimoto, Annals of Nuclear Energy, 22 (1995), p.711.

[2] Z. Su'ud, Progress in Nuclear Energy 32 (3-4) (1998), pp.571-577.

[3] Z. Su'ud, Bakrie Arbie, and Sedyartomo S, Progress of Nuclear Energy, Vol. 47 (2005), pp.212-221.

DOI: https://doi.org/10.1016/j.pnucene.2005.05.021

[4] H. Sekimoto and Zaki Su'ud, Nuclear Technology, Vol. 105, no. 3 (1995), pp.307-313.

[5] Z. Su'ud, Progress of Nuclear Energy, Vol. 50 (2008), pp.276-278.

[6] H. Sekimoto, et al, Nucl. Sci. Eng., 139 (2001), pp.1-12.

[7] K. Okumura et al. SRAC (Ver. 2002); The comprehensive neutronics calculation code system, JAERI report (2002).

[8] Y. Ohoka and H. Sekimoto, Application of CANDLE Burnup to Block Type High Temperature Gas Cooled Reactor for Incinerating Weapon Grade Plutonium, Proc. of GENES 4/ANP, 2003, Sept. 15-19, Kyoto, Japan.

DOI: https://doi.org/10.1115/icone12-49191

[9] Y. Ohoka and H. Sekimoto, Nucl. Eng. Des., 229 (2004), pp.15-23.

[10] Nur Asiah et al., Indonesian Journal of Physics, Vol. 20 No. 4 (2009).

[11] Rida S and Zaki Su'ud, Int. Journal of Energy Science and Technology (IJNEST), Vol. 4 no. 3 (2009), pp.217-222.

[12] Z. Su'ud and H. Sekimoto, Optimization of Modified Candle Burn-up Scheme Based Long Life Pb-Bi Cooled Fast Reactor with Natural Uranium as Fuel Cycle Input , PBNC 2008 Conference, Oct. 11-18 (2008), Aomori Japan.

DOI: https://doi.org/10.1504/ijnest.2010.035544

[13] Z. Su'ud and H Sekimoto, Int. Journal of Energy Science and Technology (IJNEST), Vol 5, No. 4 (2010), pp.347-368.

[14] K. Okumura, K. Kaneko and K. Tsuchihashi, SRAC95; General Purpose Neutronics Code System, , JAERI-Data/Code 96-015, Japan Atomic Energy Research Institute, Japan (2005).

[15] Z. Su'ud), FI-ITB CH1 Code: Code for Fast Reactor Design Analysis, Internal Report, ITB, Indonesia, (2000).

Paper TitlePages

Application of Modified CANDLE Burnup to Very Small Long Life Gas-Cooled Fast Reactor

Authors: Fiber Monado, Zaki Su’ud, Abdul Waris, Khairul Basar, Menik Ariani, Hiroshi Sekimoto

Abstract: Gas-cooled Fast Reactor is a good candidate for fourth generation nuclear power plant that projected to be used started in 2030. In this study, modified CANDLE burn-up strategy is adopted to create 300 MWt long life Gas-cooled Fast Reactor with metallic fuel U-10wt%Zr without enrichment. This design demonstrated excellent performance with the average discharge burn-up is about 25.9% HM.

501

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

Authors: Zaki Su’ud, Feriska H. Irka, Taufiq Imam, H. Sekimoto, P. Sidik

Abstract: 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.

530

Conceptual Design Study of Small 400 MWt Pb-Bi Cooled Modified Candle Burn-Up Based Long Life Fast Reactors

Authors: Zaki Suud, H. Sekimoto

Abstract: In this paper conceptual design study of modified CANDLE burn-up scheme based 400 MWt small long life Pb-Bi Cooled Fast Reactors with natural Uranium as Fuel Cycle Input has been performed. In this study the reactor cores are subdivided into 10 parts with equal volume in the axial directions. The natural uranium is initially put in region 1, 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, i.e. shifted the core of I’th region into I+1 region after the end of 10 years burn-up cycle. For small reactor core, it is important to apply high breeding material, so that high volume fraction of 60% fuel volume fraction nitride fuel is applied. The effective multiplication factor initially at 1.005 but then continuously increases during 10 years of burn-up. The peak power density initially about 307 W/cc but then continuously decreases to 268 at the end of 10 years burn-up cycle. Infinite multiplication factor pattern change, conversion ratio pattern change, and Pu-239 accumulation pattern change shows strong acceleration of plutonium production in the first region which is located near the 10^th region. Maximum discharged burn-up is 31.2% HM.

353

The Effects of the Total Number of Regions and Average Power Density on the Overall Performance of Modified CANDLE Burn-Up Scheme Based Gas Cooled Fast Reactors

Authors: Indah Rosidah, Maryam Afifah, Zaki Suud, Hiroshi Sekimoto, A. Ferhat

Abstract: In this study the effects of the total number of regions and average power density in Modified CANDLE burn-up scheme are studied. In the previous studies usually 10 equal axial regions are applied in Modified CANDLE burn-up scheme, and in this study 6, 8 and 10 regions Modified CANDLE burn-up scheme performance is compared and discussed. The core power level varied from 800-1000MWt. Several comparisons are performed between 10 and 8 regions Modified CANDLE, 8 and 6 regions Modified CANDLE and some additional comparison which include some changing in power level. Some general remark which we can get from this study is that reducing region with the same cycle length and power level will resulted in significant drop of effective multiplication constant especially at the beginning of life and the reduction of discharge burn-up level. On the other hand the increase of the power level with the same region number and cycle length resulted in higher effective multiplication constant value especially at the beginning of life, while at the end of life the differences are decrease. Then when we reduce the region number and increase the power level at the same time we get the mixed effect in which the system performance is relatively go back to the original case.

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