Published November 2010 | Version v1
Book Metadata-only

Methods of measuring dynamic fracture toughness on reactor pressure vessel material

Creators

  • 1. Nuclear Power Inst. of China, Chengdu (China)

Description

It was that dynamic fracture toughness was measured according to impact curve of standard Charpy-V specimens to obtain the methods of dynamic fracture toughness, while measuring the impact toughness of A508-3.The transition temperatures were attained with the transition curve of impact toughness and dynamic fracture toughness. And the feasibility of evaluating irradiation embrittlement influence was obtained using dynamic fracture toughness compared with impact toughness of the base pre-irradiated and irradiated surveillance specimens on Daya Bay nuclear power plant. It showed that evaluated irradiation embrittlement influence with dynamic fracture toughness was feasible, the same as impact toughness. (authors)

Part of:
Progress report on nuclear science and technology in China (Vol.1). Proceedings of academic annual meeting of China Nuclear Society in 2009, No.4--nuclear material

Additional details

Publishing Information

Publisher
Atomic Energy Press
Imprint Place
Beijing (China)
ISBN
978-7-5022-5040-9
Imprint Title
Progress report on nuclear science and technology in China (Vol.1). Proceedings of academic annual meeting of China Nuclear Society in 2009, No.4--nuclear material
Imprint Pagination
284 p.
Journal Page Range
p. 63-67

Conference

Title
academic annual meeting of China Nuclear Society
Acronym
'09
Dates
18-20 Nov 2009
Place
Beijing (China)

INIS

Country of Publication
China
Country of Input or Organization
China
INIS RN
44042052
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Conference
Descriptors DEI
DAYA BAY-1 REACTOR; DAYA BAY-2 REACTOR; DIAGRAMS; EMBRITTLEMENT; FRACTURE PROPERTIES; IMPACT TESTS; IRRADIATION; NUCLEAR POWER PLANTS; PHYSICAL RADIATION EFFECTS; PRESSURE VESSELS; STEEL-ASTM-A508; TRANSITION TEMPERATURE
Descriptors DEC
ALLOYS; CARBON ADDITIONS; CONTAINERS; ENRICHED URANIUM REACTORS; INFORMATION; IRON ALLOYS; IRON BASE ALLOYS; LOW ALLOY STEELS; MATERIALS TESTING; MECHANICAL PROPERTIES; MECHANICAL TESTS; NUCLEAR FACILITIES; PHYSICAL PROPERTIES; POWER PLANTS; POWER REACTORS; PWR TYPE REACTORS; RADIATION EFFECTS; REACTORS; STEELS; TESTING; THERMAL POWER PLANTS; THERMAL REACTORS; THERMODYNAMIC PROPERTIES; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
5 figs., 2 tabs., 5 refs.