Analysis of beryllium poisoning effect on liquid metal reactor with U–Be alloy fuel

Nuclear Science and Techniques - Tập 30 Số 2 - 2019
Xiaoliang Zou1,2, Yunqing Bai1, Ming-Huang Wang1, Bing Hong1,2
1Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei, China
2University of Science and Technology of China, Hefei, China

Tóm tắt

Từ khóa


Tài liệu tham khảo

Y.C. Wu, Y.Q. Bai, Y. Song et al., Conceptual design study on the China lead-based research reactor. Chin. J. Nucl. Sci. Eng. 2, 201–208 (2014). https://doi.org/10.3969/j.issn.0258-0918.2014.02.009 (in Chinese)

Y.C. Wu, Y.Q. Bai, Y. Song et al., Development strategy and conceptual design of China lead-based research reactor. Ann. Nucl. Energy 87, 511–516 (2016). https://doi.org/10.1016/j.anucene.2015.08.015

Y.C. Wu, Design and R&D progress of China lead-based reactor for ADS research facility. Engineering 2, 124–131 (2016). https://doi.org/10.1016/J.ENG.2016.01.023

Y.C. Wu, J.Q. Jiang, M.H. Wang et al., A fusion-driven subcritical system concept based on viable technologies. Nucl. Fusion 51, 103036 (2011). https://doi.org/10.1088/0029-5515/51/10/103036

Y.C. Wu, Z.P. Chen, L.Q. Hu et al., Identification of safety gaps for fusion demonstration reactors. Nat. Energy 1, 16154 (2016). https://doi.org/10.1038/nenergy.2016.154

O Reistad, P.L. Ølgaard, Russian nuclear power plants for marine applications (2006). https://www.nks.org/scripts/getdocument.php?file=111010111120029

V.V. Kalygin, A.P. Malkov, V.V. Pimenov, Effect of 3He and 6Li accumulation in beryllium blocks on the neutron-physical characteristics of the MIR reactor. Atom. Energy 104, 114–119 (2008). https://doi.org/10.1007/s10512-008-9009-x

S. Glasstone, A. Sesonske, Nuclear Reactor Engineering, vol. 81 (Springer, Berlin, 1982), p. 3. https://doi.org/10.1007/978-1-4615-2083-2

S.H. Sun, L. Zhu, H.T. Li, Research on nuclear properties of beryllium reflector in physical startup of reactor. Nucl. Power Eng. 36, 14–17 (2015). https://doi.org/10.13832/j.jnpe.2015.06.0014 (in Chinese)

H. Omar, N. Ghazi, Kh Haddad et al., Study the effect of beryllium reflector poisoning on the Syrian MNSR. Appl. Radiat. Isot. 70, 988–993 (2012). https://doi.org/10.1016/j.apradiso.2012.02.118

S. Kalcheva, B. Ponsard, E. Koonen. Reactivity Effects due to Beryllium Poisoning of BR2 (PHYSOR 2004), Chicago, 25–29 April (2004)

K. Andrzejewski, T. Kulikowska, M.Bretscher, et al., Beryllium poisoning in the MARIA reactor. Beryllium (2001). https://digital.library.unt.edu/ark:/67531/metadc720346/m2/1/high_res_d/789716.pdf

N. Lynn, S. Timms, J. Warden, et al., Radionuclide release from submarine reactors dumped in the Kara Sea//Environmental impact of radioactive releases, in Proceedings of An International Symposium (1995). https://www-pub.iaea.org/MTCD/Publications/PDF/te_0938_scr.pdf

K.J. Andrzejewski, T.A. Kulikowska, Z.E. Marcinkowska, Computations of fuel management in MARIA reactor with highly poisoned beryllium matrix. Nukleonika 53, 173–179 (2008). https://www.nukleonika.pl/www/back/full/vol53_2008/v53n4p173f.pdf

B.R. Hunt, J.M. Rosenberg, R.L. Lipsman, A guide to MATLAB: for beginners and experienced users. United Kingdom (2014). https://doi.org/10.1017/cbo9780511791284

Y.C. Wu, F.D.S. Team, CAD-based interface programs for fusion neutron transport simulation. Fusion Eng. Des. 84, 1987–1992 (2009). https://doi.org/10.1016/j.fusengdes.2008.12.041

Y.C. Wu, J. Song, H. Zheng et al., CAD-based monte carlo program for integrated simulation of nuclear system SuperMC. Ann. Nucl. Energy 82, 161–168 (2015). https://doi.org/10.1016/j.anucene.2014.08.058

J. Song, G.Y. Sun, Z.P. Chen et al., Benchmarking of CAD-based SuperMC with ITER benchmark model. Fusion Eng. Des. 89, 2499–2503 (2014). https://doi.org/10.1016/j.fusengdes.2014.05.003

B. Zhang, J. Song, G.Y. Sun et al., Criticality validation of SuperMC with ICSBEP. Ann. Nucl. Energy 87, 494–499 (2016). https://doi.org/10.1016/j.anucene.2015.10.004

J. Zou, L.M. Shang, F. Wang et al., Development of a 1200 fine group nuclear data library for advanced nuclear systems. Nucl. Sci. Tech. 28, 65 (2017). https://doi.org/10.1007/s41365-017-0216-9