Research Papers

Transmutation Study of Minor Actinides in Mixed Oxide Fueled Typical Pressurized Water Reactor Assembly

[+] Author and Article Information
Shengli Chen

Sino-French Institute of Nuclear Engineering
and Technology,
Sun Yat-Sen University,
Zhuhai 519082, Guangdong, China
e-mail: chenshl8@mail2.sysu.edu.cn

Cenxi Yuan

Sino-French Institute of Nuclear Engineering
and Technology,
Sun Yat-Sen University,
Zhuhai 519082, Guangdong, China
e-mail: yuancx@mail.sysu.edu.cn

1Corresponding author.

Manuscript received October 8, 2017; final manuscript received May 21, 2018; published online September 10, 2018. Editor: Igor Pioro.

ASME J of Nuclear Rad Sci 4(4), 041017 (Sep 10, 2018) (9 pages) Paper No: NERS-17-1142; doi: 10.1115/1.4040423 History: Received October 08, 2017; Revised May 21, 2018

The management of long-lived radionuclides in spent fuel is a key issue to achieve the closed nuclear fuel cycle and the sustainable development of nuclear energy. The partitioning-transmutation method is supposed to efficiently treat the long-lived radionuclides. Accordingly, the transmutation of long-lived minor actinides (MAs) is significant for the postprocessing of spent fuel. In the present work, the transmutations in pressurized water reactor (PWR) mixed oxide (MOX) fuel are investigated through the Monte Carlo neutron transport method. Two types of MAs are homogeneously incorporated into MOX fuel assembly with different mixing ratios. In addition, two types of design of semihomogeneous loading of 237Np in MOX fuels are studied. The results indicate an overall nice efficiency of transmutation in PWR with MOX fuel, especially for 237Np and 241Am, which are primarily generated in the current uranium oxide fuel. In addition, the transmutation efficiency of 237Np is excellent, while its inclusion has no much influence on other MAs. The flattening of power and burnup are achieved by semihomogeneous loading of MAs. The uncertainties of Monte Carlo method are negligible, while those due to nuclear data change little the conclusions of the transmutation of MAs. The transmutation of MAs in MOX fuel is expected to be an efficient method for spent fuel management.

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Von Hippel, F. N. , 2001, “ Plutonium and Reprocessing of Spent Nuclear Fuel,” Science, 293(5539), pp. 2397–2398. [CrossRef] [PubMed]
IAEA, 2009, “ Status of Minor Actinide Fuel Development,” International Atomic Energy Agency, Vienna, Austria, IAEA Nuclear Energy Series No. NF-T-4.6. https://www-pub.iaea.org/books/iaeabooks/8224/Status-of-Minor-Actinide-Fuel-Development
Liu, B. , Wang, K. , Tu, J. , Liu, F. , Huang, L. , and Hu, W. , 2014, “ Transmutation of Minor Actinides in the Pressurized Water Reactors,” Ann. Nucl. Energy, 64, pp. 86–92. [CrossRef]
Hu, W. , Liu, B. , Ouyang, X. , Tu, J. , Liu, F. , Huang, L. , Fu, J. , and Meng, H. , 2015, “ Minor Actinide Transmutation on PWR Burnable Poison Rods,” Ann. Nucl. Energy, 77, pp. 74–82. [CrossRef]
Nishihara, K. , Oigawa, H. , Nakayama, S. , Ono, K. , and Shiotani, H. , 2010, “ Impact of Partitioning and Transmutation on High-Level Waste Disposal for the Fast Breeder Reactor Fuel Cycle,” J. Nucl. Sci. Technol., 47(12), pp. 1101–1117. [CrossRef]
Meiliza, Y. , Saito, M. , and Sagara, H. , 2008, “ Protected Plutonium Breeding by Transmutation of Minor Actinides in Fast Breeder Reactor,” J. Nucl. Sci. Technol., 45(3), pp. 230–237. [CrossRef]
Wakabayashi, T. , 2002, “ Transmutation Characteristics of MA and LLFP in a Fast Reactor,” Prog. Nucl. Energy, 40(3–4), pp. 457–463. [CrossRef]
Hu, Y. , Wan, K. , and Xu, M. , 2010, “ Transmutation of MA Nuclides in Sodium Cooled MOX Fuel Fast Reactor,” Nucl. Power Eng., 1, p. 6.
Beller, D. E. , Van Tuyle, G. J. , and Bennett, D. , 2001, “ The U.S. Accelerator Transmutation of Waste Program,” Nucl. Instrum. Methods Phys. Res. A, 463(3), pp. 468–486. [CrossRef]
Herrera-Martnez, A. , Kadi, Y. , and Parks, G. , 2007, “ Transmutation of Nuclear Waste in Accelerator-Driven Systems: Thermal Spectrum,” Ann. Nucl. Energy, 34, pp. 550–563. [CrossRef]
Liang, T. , and Tang, C. , 2003, “ Transmutation of Long-Lived Nuclides,” Nucl. Tech., 26(12), pp. 935–939.
Chen, S. , and Yuan, C. , 2017, “ Transmutation of Minor Actinides and Power Flattening in PWR MOX Fuel,” Reactor Physics Asia 2017 (RPHA17) Conference, Chengdu, Sichuan, China, Aug. 24–25. https://arxiv.org/ftp/arxiv/papers/1802/1802.01659.pdf
Popov, S. G. , Carbajo, J. J. , lvanov, V. K. , and Yoder, G. L. , 2000, “ Thermophysical Properties of MOX and UO2 Fuels Including the Effects of Irradiation,” Oak Ridge National Laboratory, Oak Ridge, TN, No. ORNL/TM-2000/351. https://rsicc.ornl.gov/fmdp/tm2000-351.pdf
Chen, S. , and Yuan, C. , 2017, “ Neutronic Analysis on Potential Accident Tolerant Fuel-Cladding Combination U3Si2-FeCrAl,” Sci. Technol. Nucl. Install., 2017, p. 3146985.
Chadwick, M. B. , Oblozinsky, P. , Herman, M. , Greene, N. M. , McKnight, R. D. , Smith, D. L. , Young, P. G. , MacFarlane, R. E. , Hale, G. M. , Frankle, S. C. , and Kahler, A. C. , 2006, “ ENDF/B-VII. 0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology,” Nucl. Data Sheets, 107(12), pp. 2931–3060. [CrossRef]
Wang, K. , Li, Z. , She, D. , Xu, Q. , Qiu, Y. , Yu, J. , Sun, J. , Fan, X. , and Yu, G. , 2015, “ RMC-CA Monte Carlo Code for Reactor Core Analysis,” Ann. Nucl. Energy, 82, pp. 121–129. [CrossRef]
Li, Z. , Wang, K. , and Zhang, X. , 2011, “ Research on Applying Neutron Transport Monte Carlo Method in Materials With Continuously Varying Cross Sections,” M&C 2011, Rio de Janeiro, RJ, Brazil, May 8–12, pp. 1–15. http://www.iaea.org/inis/collection/NCLCollectionStore/_Public/48/022/48022323.pdf?r=1
Liu, S. , Yuan, Y. , Yu, J. , and Wang, K. , 2016, “ Development of on-the-Fly Temperature-Dependent Cross Sections Treatment in RMC Code,” Ann. Nucl. Energy, 94, pp. 144–149. [CrossRef]
Yu, J. , Li, S. , Wang, K. , Wang, G. , and Yu, G. , 2013, “ The Development and Validation of Nuclear Cross Section Processing Code for Reactor-RXSP,” ASME Paper No. Paper No. ICONE21-15442.
Qiu, Y. , Aufiero, M. , Wang, K. , and Fratoni, M. , 2016, “ Development of Sensitivity Analysis Capabilities of Generalized Responses to Nuclear Data in Monte Carlo Code RMC,” Ann. Nucl. Energy, 97, pp. 142–152. [CrossRef]
Qiu, Y. , Shang, X. , Tang, X. , Liang, J. , and Wang, K. , 2016, “ Computing Eigenvalue Sensitivity Coefficients to Nuclear Data by Adjoint Superhistory Method and Adjoint Wielandt Method Implemented in RMC Code,” Ann. Nucl. Energy, 87, pp. 228–241. [CrossRef]
She, D. , Liu, Y. , Wang, K. , Yu, G. , Forget, B. , Romano, P. K. , and Smith, K. , 2013, “ Development of Burnup Methods and Capabilities in Monte Carlo Code RMC,” Ann. Nucl. Energy, 51, pp. 289–294. [CrossRef]
She, D. , Wang, K. , and Yu, G. , 2013, “ Development of the Point-Depletion Code DEPTH,” Nucl. Eng. Des., 258, pp. 235–240. [CrossRef]
Parks, C. V. , 1992, “ Overview of ORIGEN2 and ORIGEN-S: Capabilities and Limitations,” Third International Conference on High Level Radioactive Waste Management, Las Vegas, NV, Apr. 12–16, pp. 57–63. https://inis.iaea.org/search/search.aspx?orig_q=RN:23037442
Yuan, C. , Suzuki, T. , Otsuka, T. , Xu, F. , and Tsunoda, N. , 2012, “ Study of B, C, N, and O Isotopes Based on VMU,” Phys. Rev. C, 85(6), p. 064324. [CrossRef]
Yuan, C. , Qi, C. , Xu, F. , Suzuki, T. , and Otsuka, T. , 2014, “ Mirror Energy Difference and the Structure of Loosely Bound Proton-Rich Nuclei Around A=20,” Phys. Rev. C, 89(4), p. 044327. [CrossRef]
Yuan, C. , Liu, Z. , Xu, F. , Walker, P. M. , Podolyak, Z. , Xu, C. , Ren, Z. Z. , Ding, B. , Liu, X. Y. , and Xu, H. S. , 2016, “ Isomerism in the South-East of 132Sn and a Predicted Neutron-Decaying Isomer in 129Pd,” Phys. Lett. B, 762, pp. 237–242. [CrossRef]
Otsuka, T. , Honma, M. , Mizusaki, T. , Shimizu, N. , and Utsuno, Y. , 2001, “ Monte Carlo Shell Model for Atomic Nuclei,” Prog. Part. Nucl. Phys., 47(1), pp. 319–400. [CrossRef]
Broeders, C. H. M. , Kiefhaber, E. , and Wiese, H. W. , 2000, “ Burning Transuranium Isotopes in Thermal and Fast Reactors,” Nucl. Eng. Des., 202(2–3), pp. 157–172. [CrossRef]
Iwasaki, T. , 2002, “ A Study of Transmutation of Minor-Actinide in a Thermal Neutron Field of the Advanced Neutron Source,” Prog. Nucl. Energy, 40(3–4), pp. 481–488. [CrossRef]
NEA, 2017, “ JEFF-3.3 Nuclear Data Library,” OECD Nuclear Energy Agency, Paris, France, accessed Nov. 20, 2017, https://www.oecd-nea.org/dbdata/JEFF33
Yuan, C. , Wang, X. , and Chen, S. , 2016, “ A Simple Formula for Local Burnup and Isotope Distributions Based on Approximately Constant Relative Reaction Rate,” Sci. Technol. Nucl. Install., 2016, p. 6980547.
Chen, S. , Yuan, C. , and Guo, D. , 2018, “ Radial Distributions of Power and Isotopic Concentration in Candidate ATF U3Si2 and UO2/U3Si2 Fuel With FeCrAl Cladding,” preprint arXiv:1802.03574. https://arxiv.org/abs/1802.03574
Yuan, C. , 2016, “ Uncertainty Decomposition Method and Its Application to the Liquid Drop Model,” Phys. Rev. C, 93(3), p. 034310. [CrossRef]
Yuan, C. , 2017, “ Impact of Off-Diagonal Cross-Shell Interaction on 14C,” Chin. Phys. C, 41(10), p. 104102. [CrossRef]
Chen, S. , 2017, “ Interpretation of the PROFIL(2) Experiments for the Calculation of the Capture Cross Sections and Corresponding Covariance Matrices of the Main Fission Products,” M.S. thesis, Sun Yat-sen University, Guangdong, China.


Grahic Jump Location
Fig. 1

17 × 17 PWR lattice configuration

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Fig. 2

Relative power distribution in the high plutonium concentration MOX fuel assembly at the BOL

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Fig. 3

Configuration of the 17 × 17 PWR fuel assembly with 32 (left) and 92 (right) MAs loaded pins

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Fig. 4

Actinide concentration in the high plutonium concentration MOX fuel without MA loading

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Fig. 5

Actinide concentration in the low plutonium concentration MOX fuel without MA loading

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Fig. 6

Minor actinide concentration in the high (left) and low (right) plutonium concentration MOX fuels with 1% mixed MAs loading

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Fig. 7

Minor actinide concentration in the high (left) and low (right) plutonium concentration MOX fuels with 1% 237Np loading

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Fig. 8

kinf for no MA loading, homogeneous 1% mixed MAs loading, and homogeneous 1% 237Np loading cases in the high (left) and low (right) plutonium concentration MOX fuels

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Fig. 9

kinf for no MA loading, 32 0.5% 237Np loaded pins, 92 0.5% 237Np loaded pins, and all 0.5% 237Np loaded pins in the high (left) and low (right) plutonium concentration MOX fuels



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