Published April 2016 | Version v1
Book Metadata-only

Study on the Compatibility between U-10Mo and N18 Zirconium Alloy

Creators

  • 1. Science and Technology on Reactor Full and Materials Laboratory Nuclear Power Institute of China, Chengdu (China)
  • 2. China Academy of Engineering Physics, Jiangyou (China)

Description

The compatibility between U-Mo alloy and Zirconium alloy was studied in this paper. The diffusion-couple was prepared by coated hot-rolling and annealed at 750 ℃ and 850 ℃ for 10 and 50 hours. The result shows that the diffusion-layer has delaminated between U-Mo alloy and Zirconium alloy, and diffusion-layer has a complicated composition with the Mo2Zr second precipitate. XRD result shows that the composition of diffusion-layer is the Mo2Zr, UZr2 and U. The diffused mechanism of U-Mo and Zirconium is that the atom of U and Mo diffuse into Zirconium alloy, then Mo and Zr form Mo2Zr firstly and the U continuously through out Mo2Zr formed γ-(U, Zr) solid- solution. The U-Mo alloy has good compatibility with Zirconium alloy. (authors)

Part of:
Progress report on nuclear science and technology in China (Vol.4). Proceedings of academic annual meeting of China Nuclear Society in 2015, No.5--Nuclear Material sub-volume

Additional details

Publishing Information

Publisher
Atomic Energy Press
Imprint Place
Beijing (China)
ISBN
978-7-5022-7103-9
Imprint Title
Progress report on nuclear science and technology in China (Vol.4). Proceedings of academic annual meeting of China Nuclear Society in 2015, No.5--Nuclear Material sub-volume
Imprint Pagination
381 p.
Journal Page Range
p. 332-337

Conference

Title
2015 academic annual meeting of China Nuclear Society
Dates
21-24 Sep 2015
Place
Mianyang (China)

INIS

Country of Publication
China
Country of Input or Organization
China
INIS RN
53085134
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ALLOY NUCLEAR FUELS; ANNEALING; CLADDING; COMPATIBILITY; DIFFUSION; ELECTRON MICROSCOPES; NUCLEAR FUELS; REACTORS; TEMPERATURE RANGE 1000-4000 K; ZIRCONIUM ALLOYS
Descriptors DEC
ALLOYS; DEPOSITION; ENERGY SOURCES; FUELS; HEAT TREATMENTS; MATERIALS; MICROSCOPES; NUCLEAR FUELS; REACTOR MATERIALS; SOLID FUELS; SURFACE COATING; TEMPERATURE RANGE; TRANSITION ELEMENT ALLOYS

Optional Information

Notes
7 figs., 1 tab., 8 refs.