Results 171 to 180 of about 1,250 (204)
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Evaluation of Irradiation Embrittlement of the Chinese RPV Steels
Volume 6A: Materials and Fabrication, 2019Abstract Reactor pressure vessel (RPV) is considered to be irreplaceable, which is the most limiting factor for the lifetime of a nuclear power plant. This paper aims to introduce our project for the evaluation of the irradiation embrittlement for the Chinese RPV forging.
Yupeng Cao +6 more
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Irradiation-Embrittlement of Reactor Pressure Vessel Steel
18th International Conference on Nuclear Engineering: Volume 5, 2010Irradiated for 4 cycles inside the reactor, the irradiation surveillance capsule (ISC) was withdrawn and transported to Nuclear Power Institute of China (NPIC) for dismantling in the hot cell. This paper presented tensile tests and Charpy-V impact tests on non-irradiated and irradiated specimens. Tensile tests were performed at room temperature and 300
Guoyun Li +4 more
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Irradiation embrittlement characterization of the EUROFER 97 material
Journal of Nuclear Materials, 2011The paper summarizes original results of irradiation embrittlement study of EUROFER 97 material that has been proposed as one candidate of structural materials for future fusion energy systems and GEN IV. Test specimens were manufactured from base metal as well as from weld metal and tested in initial unirradiated condition and also after neutron ...
M. Kytka, M. Brumovsky, M. Falcnik
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Determination of Neutron Damage Parameters for Irradiation Embrittlement
1983Programs for improvement in evaluation of damage exposure parameters for irradiation embrittlement in pressure vessel steels are currently under way. Results will be implemented through a series of ASTM standards which will enable radiation damage to be consistently predicted with increased confidence and with well-defined uncertainty trends.
EP Lippincott, WN McElroy
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Irradiation Embrittlement of Advanced Pressure Vessel Steels
1987Seven commercial steels in the form of plate, forging, or weldments supplied by Japan, France, and the Federal Republic of Germany to the International Atomic Energy Agency (IAEA) Co-ordinated Research Programme on “Analysis of the Behaviour of Advanced Reactor Pressure Vessel Steels under Neutron Irradiation” were irradiated at 290°C to a nominal fast
KS Sivaramakrishnan +5 more
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Solutions to the Problems of High-Temperature Irradiation Embrittlement
1967The effects of irradiation on high-temperature mechanical properties of structural materials is described using Type 304 stainless steel as an example. The general effect is one in which the grain-boundary fracture process, but not the deformation process, is affected.
W. R. Martin, J. R. Weir
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The Dependence of Radiation Hardening and Embrittlement on Irradiation Temperature
1996Assessments of the hardening and embrittlement of pressure vessel steels and welds as a function of neutron dose use trend curves derived from surveillance programmes and accelerated irradiation data. A temperature dependent factor is incorporated for assessing vessel locations operating at different temperatures.
RB Jones, TJ Williams
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Study on irradiation embrittlement behavior of reactor pressure vessels by machine learning methods
Annals of Nuclear Energy, 2023exaly
Journal of Pressure Vessel Technology, Transactions of the ASME, 2021
Hisashi Takamizawa, Yutaka Nishiyama
exaly
Hisashi Takamizawa, Yutaka Nishiyama
exaly