Published April 2020 | Version v1
Book Metadata-only

Study on thermal deformation behavior of FeCrAl

Creators

  • 1. Science and Technology on Reactor Fuel and Matcrials Laboratory, Chengdu (China)
  • 2. National Energy Research and Development Center on Advanced Nuclear Fuel Element, Chengdu (China)

Description

FeCrAl alloy has become the main development direction of ATF cladding materials in the world's nuclear powers due to its good inherent safety. In this paper, Gleeble thermal simulator was used to study the effect of thermal deformation behavior on FeCrAl alloy The hot working drawing is constructed. Suitable for processing area: 800 ∼ 950 ℃, 1 ∼ 10 s-1; 950 ∼ 1000 ℃, 0.05 s-1. (authors)

Part of:
Progress report on nuclear science and technology in China (Vol.6). Proceedings of academic annual meeting of China Nuclear Society in 2019, No.5--Nuclear Material sub-volume

Additional details

Publishing Information

Publisher
China Atomic Energy Press
Imprint Place
Beijing (China)
ISBN
978-7-5221-0522-2
Imprint Title
Progress report on nuclear science and technology in China (Vol.6). Proceedings of academic annual meeting of China Nuclear Society in 2019, No.5--Nuclear Material sub-volume
Imprint Pagination
196 p.
Journal Page Range
p. 183-186

Conference

Title
2019 academic annual meeting of China Nuclear Society
Dates
20-23 Aug 2019
Place
Baotou (China)

INIS

Country of Publication
China
Country of Input or Organization
China
INIS RN
53115026
Subject category
S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ACCIDENT-TOLERANT NUCLEAR FUELS; ALUMINIUM ALLOYS; CHROMIUM ALLOYS; DEFORMATION; DRAWING; FUEL CANS; HEAT RESISTING ALLOYS; HOT WORKING; IRON ALLOYS
Descriptors DEC
ALLOYS; ENERGY SOURCES; FABRICATION; FUELS; HEAT RESISTANT MATERIALS; MATERIALS; MATERIALS WORKING; NUCLEAR FUELS; REACTOR MATERIALS; TRANSITION ELEMENT ALLOYS

Optional Information

Notes
8 figs., 5 refs.