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Experimental Investigation of 14C in the Primary Coolant of the 10 MW High Temperature Gas-Cooled Reactor

Published online by Cambridge University Press:  29 April 2019

F Xie
Affiliation:
Institute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Tsinghua University, Beijing 100084, China
W Peng
Affiliation:
Institute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Tsinghua University, Beijing 100084, China
J Cao
Affiliation:
Institute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Tsinghua University, Beijing 100084, China
X Feng*
Affiliation:
Institute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Tsinghua University, Beijing 100084, China
L Wei
Affiliation:
Institute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Tsinghua University, Beijing 100084, China
J Tong
Affiliation:
Institute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Tsinghua University, Beijing 100084, China
F Li
Affiliation:
Institute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Tsinghua University, Beijing 100084, China
K Sun
Affiliation:
Massachusetts Institute of Technology, Nuclear Reactor Laboratory, Cambridge, MA 02139, USA
*
*Corresponding author. Email: fengxiaogui@tsinghua.edu.cn.

Abstract

The very high temperature reactor (VHTR) is a development of the high-temperature gas-cooled reactors (HTGRs) and one of the six proposed Generation IV reactor concept candidates. The 10 MW high temperature gas-cooled reactor (HTR-10) is the first pebble-bed gas-cooled test reactor in China. A sampling system for the measurement of carbon-14 (14C) was established in the helium purification system of the HTR-10 primary loop, which could sample 14C from the coolant at three locations. The results showed that activity concentration of 14C in the HTR-10 primary coolant was 1.2(1) × 102 Bq/m3 (STP). The production mechanisms, distribution characteristics, reduction routes, and release types of 14C in HTR-10 were analyzed and discussed. A theoretical model was built to calculate the amount of 14C in the core of HTR-10 and its concentration in the primary coolant. The activation reaction of 13C has been identified to be the dominant 14C source in the core, whereas in the primary coolant, it is the activation of 14N. These results can supplement important information for the source term analysis of 14C in HTR-10 and promote the study of 14C in HTGRs.

Type
Research Article
Copyright
© 2019 by the Arizona Board of Regents on behalf of the University of Arizona 

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References

REFERENCES

Aghoyeh, RG, Khalafi, H. 2012. Evaluation of tritium and carbon-14 radioactivity in primary loop of Tehran Research Reactor (TRR). Progress in Nuclear Energy 60:135139.CrossRefGoogle Scholar
Aquilonius, K, Hallberg, B. 2005. Process-oriented dose assessment model for 14C due to releases during normal operation of a nuclear power plant. Journal of Environmental Radioactivity 82:267283.CrossRefGoogle ScholarPubMed
Bäumer, R, Barnert, H. 1990. AVR-experimental high-temperature reactor: 21 years of successful operation for a future energy technology. Düsseldorf, Germany: The Association of German Engineers (VDI-Verlag GmbH).Google Scholar
Begg, FH, Cook, GT, Baxter, MS, Scott, EM, McCartney, M. 1992. Anthropogenic radiocarbon in the eastern Irish Sea and Scottish Coastal Waters. Radiocarbon 34(3):707716.CrossRefGoogle Scholar
Davis, W Jr. 1977. Carbon-14 production in nuclear reactors. ORNL/NUREG/TM-12, Oak Ridge National Laboratory, Oak Ridge, TN, USA.Google Scholar
Dias, CM, Telles, EC, Santos, RV, Stenström, K, Nícoli, IG, Corrêa, RdS, Skog, G. 2009. 14C, δ13C and total C content in soils around a Brazilian PWR nuclear power plant. Journal of Environmental Radioactivity 100:348353.CrossRefGoogle Scholar
Fachinger, J, Lensa, W, Podruhzina, T. 2008. Decontamination of nuclear graphite. Nuclear Engineering and Design 238:30863091.CrossRefGoogle Scholar
Feng, X, He, Q, Wang, J, Chen, J. 2012. The long-term stability on basic performances of a diisopropylnaphthalene-based liquid scintillation cocktail. Applied Radiation Isotope. 70(8):15361540.CrossRefGoogle ScholarPubMed
Frolov, A. 2002. Carbon-14 in gas-aerosol release from NPP with WWER type reactor. Topical report, SPAEP.Google Scholar
Hoinkis, E, Eatherly, WP, Krautwasser, P, Robens, E. 1986. Corrosion- and irradiation-induced porosity changes of a nuclear graphitic material. Journal of Nuclear Materials 141–143(1):8795.CrossRefGoogle Scholar
Hou, X. 2005. Rapid analysis of 14C and 3H in graphite and concrete for decommissioning of nuclear reactor. Applied Radiation and Isotopes 62:871882.CrossRefGoogle ScholarPubMed
Institute of Nuclear and New Energy Technology (INET), Tsinghua University. 2000. Final safety analysis report of 10MW high temperature gas-cooled reactor.Google Scholar
International Atomic Energy Agency (IAEA). 2004. Management of waste containing tritium and carbon-14. Technical Reports Series 421. Vienna.Google Scholar
Ješkovský, M, Povinec, PP, Steier, P, Šivo, A, Richtáriková, M, Golser, R. 2015. Retrospective study of 14C concentration in the vicinity of NPP Jaslovské Bohunice using tree rings and the AMS technique. Nuclear Instruments and Methods in Physics Research B 361:129132.CrossRefGoogle Scholar
Khripunov, VI, Kurbatov, DK, Subbotin, ML. 2008. Carbon-14 source terms and generation in fusion power cores. Journal of Fusion Energy 27(4):241249.CrossRefGoogle Scholar
Li, H, Liu, X, Xie, F, Jia, F. 2017. Experimental study on the content and distribution of key nuclides in an irradiated graphite sphere of HTR-10. Nuclear Engineering and Design 323:3945.CrossRefGoogle Scholar
Liu, X, Huang, X, Xie, F, Jia, F, Feng, X, Li, H. 2017. Source term analysis of irradiated graphite in the core of HTR-10. Science and Technology and Nuclear Installations 2017:2614890(1–6).CrossRefGoogle Scholar
Lu, Z, Chen, X, Wei, L, Zhou, X, Zhang, J, Liu, B. 2016. Pore structure and moisture absorption property of carbon materials in HTR. Atomic Energy Science and Technology 50(3):274278. In Chinese.Google Scholar
Lu, Z, Chen, X, Zhou, X, Zhang, J, Jiang, Z, Liu, S. 2013. Research on moisture absorption property and surface characteristics measurement of graphite/carbon materials in HTR-PM. Internal Report, Beijing: Institute of Nuclear and New Energy Technology, Tsinghua University.Google Scholar
Marsden, BJ, Hopkinson, KL, Wickham, AJ. 2002. The chemical form of carbon-14 within graphite. Nirex, TE2928/002.Google Scholar
Ministry of Environment Protection of China (MEPC). 2011. Regulations for environmental radiation protection of nuclear power plant. Tech. Rep. GB 6249–2011.Google Scholar
Mook, WG, van der Plicht, J. 1999. Reporting 14C activities and concentrations. Radiocarbon 41(3):227239.CrossRefGoogle Scholar
Muir, GKP, Cook, GT, MacKenzie, AB, MacKinnon, G, Gulliver, P. 2015. Anomalous 14C enrichments in the eastern UK coastal environment. Radiocarbon 57(3):337345.CrossRefGoogle Scholar
Nuclear Decommissioning Authority (NDA), 2012. Geological disposal carbon-14 project- Phase 1 report. NDA Report no. NDA/RWMD/092.Google Scholar
Park, JH, Hong, W, Xu, X, Park, G, Sung, KS, Sung, K, Lee, J, Nakanishi, T, Park, H. 2015. The distribution of Δ14C in Korea from 2010 to 2013. Nuclear Instruments and Methods in Physics Research B 361:609613.CrossRefGoogle Scholar
Pohl, RO. 1976. Nuclear energy: health impact of carbon-14. Radiation and Environmental Biophysics 13:315327.CrossRefGoogle ScholarPubMed
SDEC France. 2013. Operational manual of carbon-14 sampler “HAGUE 7000”.Google Scholar
Smith, TE, Mccrory, S, Dunzik-Gougar, ML. 2013. Limited oxidation of irradiated graphite waste to remove surface carbon-14. Nuclear Engineering and Technology 45(2):211218.CrossRefGoogle Scholar
U.S. DOE Nuclear Energy Research Advisory Committee (NERAC) and the Generation IV International Forum (GIF). 2002. A technology roadmap for generation IV nuclear energy systems. GIF-002-00.Google Scholar
Val’skii, G. 1976. Yields of light nuclei in ternary fission. Soviet Journal of Nuclear Physics 24(2):140144.Google Scholar
Wang, S, Pi, Y, Xie, F, Li, H, Cao, J. 2014. Study on 14C content in post-irradiation graphite spheres of HTR-10. Atomic Energy Science and Technology 48(Suppl.):506510. In Chinese.Google Scholar
Wei, L, Xie, F, Chen, X, Ma, T, Tong, J, Li, F. 2016. Summary and experience feedback on the restart and power operation after a long-time shutdown of HTR-10. Proceedings of the 8th International Topical Meeting on High Temperature Reactor Technology (HTR 2016). Las Vegas (NV).Google Scholar
Wichner, RP, Dyer, FF. 1980. Carbon-14 production in the peach bottom HTGR core. Oak Ridge National Laboratory, ORNL-5597.Google Scholar
Wu, Z, Lin, D, Zhong, D. 2002. The design features of the HTR-10. Nuclear Engineering and Design 218:2532.CrossRefGoogle Scholar
Xie, F, Cao, J, Chen, Z, Dong, Y. 2015. The design and study of the radioactive graphite dust experimental system in the primary loop of the HTR-10. Atomic Energy Science and Technology 49(4):744749. In Chinese.Google Scholar
Xie, F, Cao, J, Feng, X, Liu, X, Tong, J, Wang, H, Dong, Y, Zhang, Z, Loyalka, SK. 2017. Experimental research on the radioactive dust in the primary loop of HTR-10. Nuclear Engineering and Design 324:372378.CrossRefGoogle Scholar
Xie, F, Cao, J, Feng, X, Tong, J, Dong, Y, Zhang, Z, Scarlat, RO. 2018a. Study of tritium in the primary loop of HTR-10: experiment and theoretical calculations. Progress in Nuclear Energy 105:99105.CrossRefGoogle Scholar
Xie, F, Li, H, Liu, X, Chen, J, Li, C, Chen, X, Verfondern, K. 2018b. A comprehensive study on source terms in irradiated graphite spheres of HTR-10. Annals of Nuclear Energy 122:352365.CrossRefGoogle Scholar
Xu, S, Cook, GT, Cresswell, AJ, Dunbar, E, Freeman, SPHT, Hou, X, Jacobsson, P, Kinch, HR, Naysmith, P, Sanderson, DCW, Tripney, BG. 2016. Radiocarbon releases from the 2011 Fukushima nuclear accident. Scientific Reports 6:36947(1–9).Google ScholarPubMed
Xu, Y, Li, H, Xie, F, Cao, J, Tong, J. 2017. Source term analysis of tritium in HTR-10. Fusion Science and Technology 71:671678.CrossRefGoogle Scholar
Xu, Y, Zuo, K. 2002. Overview of the 10 MW high temperature gas cooled reactor—test module project. Nuclear Engineering and Design 218:1323.CrossRefGoogle Scholar
Yao, M, Wang, R, Liu, Z, He, X, Li, J. 2002. The helium purification system of the HTR-10. Nuclear Engineering and Design 218:163167.CrossRefGoogle Scholar
Yim, M-S, Caron, F. 2006. Life cycle and management of carbon-14 from nuclear power generation. Progress in Nuclear Energy 48:236.CrossRefGoogle Scholar
Zhang, Z, Yu, S. 2002. Future HTGR developments in China after the criticality of the HTR-10. Nuclear Engineering and Design 218:249257.CrossRefGoogle Scholar
Zhu, J, Li, Z. 2010. Research on quality of helium gas in primary system of 10 MW high-temperature gas-cooling reactor. Atomic Energy Science and Technology 44(Suppl.):274278. In Chinese.Google Scholar