Analysis of beryllium poisoning effect on liquid metal reactor with U–Be alloy fuel
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摘要
A liquid metal reactor(LMR) loaded with a fuel compound of uranium and beryllium(U-Be alloy fuel),which was cooled by a lead-bismuth eutectic alloy(PbBi),has been applied in Russian Alfa-class nuclear submarines.Because of the large amount of beryllium in the core, the reaction between the beryllium atoms and neutrons could result in the accumulation of 3 He and 6 Li, which are called the "poisoned elements" owing to their large thermal neutron capture cross section. The accumulation of neutron absorber can affect the performance of a reactor. In this study, the Super Multi-functional Calculation Program(SuperMC) code, which was developed by Institute of Nuclear Energy Safety Technology of the Chinese Academy of Sciences(INEST, CAS), was adopted to illustrate the influence of beryllium on an LMR.
A liquid metal reactor(LMR) loaded with a fuel compound of uranium and beryllium(U-Be alloy fuel),which was cooled by a lead-bismuth eutectic alloy(PbBi),has been applied in Russian Alfa-class nuclear submarines.Because of the large amount of beryllium in the core, the reaction between the beryllium atoms and neutrons could result in the accumulation of 3 He and 6 Li, which are called the "poisoned elements" owing to their large thermal neutron capture cross section. The accumulation of neutron absorber can affect the performance of a reactor. In this study, the Super Multi-functional Calculation Program(SuperMC) code, which was developed by Institute of Nuclear Energy Safety Technology of the Chinese Academy of Sciences(INEST, CAS), was adopted to illustrate the influence of beryllium on an LMR.
A liquid metal reactor(LMR) loaded with a fuel compound of uranium and beryllium(U-Be alloy fuel),which was cooled by a lead-bismuth eutectic alloy(PbBi),has been applied in Russian Alfa-class nuclear submarines.Because of the large amount of beryllium in the core, the reaction between the beryllium atoms and neutrons could result in the accumulation of 3 He and 6 Li, which are called the "poisoned elements" owing to their large thermal neutron capture cross section. The accumulation of neutron absorber can affect the performance of a reactor. In this study, the Super Multi-functional Calculation Program(SuperMC) code, which was developed by Institute of Nuclear Energy Safety Technology of the Chinese Academy of Sciences(INEST, CAS), was adopted to illustrate the influence of beryllium on an LMR.
引文
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15.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
16.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
17.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
18.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
19.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
20.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
2.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.anu cene.2015.08.015
3.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
4.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
5.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
6.O Reistad,P.L.?lgaard,Russian nuclear power plants for marine applications(2006).https://www.nks.org/scripts/getdocument.php?file=111010111120029
7.V.V.Kalygin,A.P.Malkov,V.V.Pimenov,Effect of3He and6Li 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
8.S.Glasstone,A.Sesonske,Nuclear Reactor Engineering,vol.81(Springer,Berlin,1982),p.3.https://doi.org/10.1007/978-1-4615-2083-2
9.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)
10.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
11.S.Kalcheva,B.Ponsard,E.Koonen.Reactivity Effects due to Beryllium Poisoning of BR2(PHYSOR 2004),Chicago,25-29April(2004)
12.K.Andrzejewski,T.Kulikowska,M.Bretscher,et al.,Beryllium poisoning in the MARIA reactor.Beryllium(2001).https://digi tal.library.unt.edu/ark:/67531/metadc720346/m2/1/high_res_d/789716.pdf
13.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/Publica tions/PDF/te_0938_scr.pdf
14.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
15.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
16.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
17.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
18.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
19.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
20.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