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2019 | OriginalPaper | Buchkapitel

14. Neutronics Experiments of Fusion Systems

verfasst von : Yican Wu

Erschienen in: Neutronics of Advanced Nuclear Systems

Verlag: Springer Singapore

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Abstract

Since the 1950 s, with the development of fusion systems, many fusion neutron source facilities have been built around the world. A series of experiments have been performed to support the development of fusion systems with these facilities that aim to validate the reliability of neutronics design, the precision of nuclear data and the correctness of computational methods and tools [1]. In this chapter, a general introduction of fusion neutronics experiments is first presented. Then, certain typical experiments such as activation experiments, tritium breeding experiments, irradiation experiments, and shielding experiments are introduced. Last, the prospects for the development of fusion neutronics experiments are discussed.

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Vorheriges Kapitel Neutronics Experiments of Advanced Fission Systems

Nächstes Kapitel Neutronics Experiments of Hybrid Nuclear Systems

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Wu YC (2017) Fusion neutronics. Springer nature Singapore Pte Ltd, SingaporeCrossRef

Batistoni P, Angelone M, Fischer U et al (2012) Neutronics experiments for uncertainty assessment of tritium breeding in HCPB and HCLL blanket mock-ups irradiated with 14 MeV neutrons. Nucl Fusion 52(8):083014CrossRef

Xiong HH, Chen SZ, Wang YF et al (2018) Neutronics experiment on DFLL-TBM mock-up irradiated with D-T fusion neutrons. Nucl Sci Eng 38(1):75–80 (in Chinese)

Huang QY, Li C, Li Y et al (2007) Progress in development of China low activation martensitic steel for fusion application. J Nucl Mater 367–370:142–146CrossRef

Ge HE (2015) Hardening behaviour of CLAM steel induced by neutron irradiation. University of Science and Technology of China, Hefei (in Chinese)

Xin JP, Liu SJ, Li CJ et al (2016) Tensile and impact properties of CLAM steel after neutron irradiation to 2.98dpa at 430 ℃. Nucl Sci Eng 36(4):487–491

Ge HE, Peng L, Dai Y et al (2016) Tensile properties of CLAM steel irradiated up to 20.1 dpa in STIP-V. J Nucl Mater 468:240–245CrossRef

10.

Hu XX, Koyanagi T, Fukuda M et al (2016) Irradiation hardening of pure tungsten exposed to neutron irradiation. J Nucl Mater 480:235–243CrossRef

11.

Fukuda M, Hasegawa A, Tanno T et al (2013) Property change of advanced tungsten alloys due to neutron irradiation. J Nucl Mater 442:S273–S276CrossRef

12.

Kalinin GM, Artyugin AS, Yvseev MV et al (2011) The effect of irradiation on tensile properties and fracture toughness of CuCrZr and CuCrNiSi alloys. J Nucl Mater 417:908–911CrossRef

13.

Li MM, Sokolov MA, Zinkle SJ (2009) Tensile and fracture toughness properties of neutron-irradiated CuCrZr. J Nucl Mater 393:36–46CrossRef

14.

Weber HW (2011) Radiation effects on superconducting fusion magnet components. Int J Mod Phys E 20(06):1325–1378CrossRef

15.

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16.

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17.

Angelonea M, Batistonia P, Moroa F (2012) Neutronics analysis and nuclear heating measurement up to the TFC in a mock-up of the ITER in board shield. Fusion Eng Des 87:910–915CrossRef

18.

Batistoni P, Angelone M, Fischer U et al (2000) Neutron streaming experiment at FNG: results and analysis. Fusion Eng Des 51–52(1):653–661

19.

Batistoni P, Angelone M, Fischer U et al (1999) Neutronics experiment on a mock-up of the ITER shielding blanket at the Frascati neutron generator. Fusion Eng Des 47(1):25–60CrossRef

20.

Vasilopoulou T, Stamatelatos IE, Batistoni P et al (2015) Neutron streaming along ducts and labyrinths at the JET biological shielding: Effect of concrete composition. Radiat Phys Chem 116:359–364CrossRef

21.

Wakisaka M, Kaneko J, Fujita F et al (2005) Analysis of neutron propagation from the skyshine port of a fusion neutron source facility. Nucl Instrum Methods Phys Res 554:347–355CrossRef

Titel: Neutronics Experiments of Fusion Systems
verfasst von: Yican Wu
Verlag: Springer Singapore
Buch: Neutronics of Advanced Nuclear Systems
Print ISBN: 978-981-13-6519-5

Electronic ISBN: 978-981-13-6520-1

Copyright-Jahr: 2019
DOI: https://doi.org/10.1007/978-981-13-6520-1_14