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Calculation of the Displacement Cross-section for Structural Materials
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作者 korepanova nadezda Gu Long 《IMP & HIRFL Annual Report》 2018年第1期216-217,共2页
A structural material in a nuclear reactor is damaged by neutrons.Neutrons transfer their kinetic energy to atoms,which in its turn start to displace other atoms from its sites and create vacancies and interstitial at... A structural material in a nuclear reactor is damaged by neutrons.Neutrons transfer their kinetic energy to atoms,which in its turn start to displace other atoms from its sites and create vacancies and interstitial atoms when displaced atoms come to rest in a location between lattice sites.The vacancy-interstitial pair is known as Frankel Pair(FP).The FPs are key to radiation effects in materials.Their appearance is the main cause of defects formation and change in physical properties,such as a change in shape,increasing of hardness and embrittlement,reduction in ductility,and inducing cracking. 展开更多
关键词 DUCTILITY SECTION VACANCY
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Evaluation of Cladding Swelling in CiADS Radiation Environment
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作者 korepanova nadezda Gu Long Zhang Lu 《IMP & HIRFL Annual Report》 2018年第1期217-218,共2页
The integrity of materials in reactors are associated with safety and reliability of a nuclear power plant.One of the most vulnerable components of a nuclear reactor is a cladding of a fuel pin,because of more aggress... The integrity of materials in reactors are associated with safety and reliability of a nuclear power plant.One of the most vulnerable components of a nuclear reactor is a cladding of a fuel pin,because of more aggressive environment,higher temperature and higher radiation level compare with other components.For CiADS the 15-15Ti steel has been chosen as a cladding material due to its properties.The steel was specially developed as a cladding material with increased swelling resistance.The aim of our work is to evaluate cladding swelling,because it leads to embrittlement and then,as the result,to a failure. 展开更多
关键词 CLADDING STEEL properties.
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Calculation of the Displacement Cross-section for 15-15Ti steel
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作者 korepanova nadezda Gu Long 《IMP & HIRFL Annual Report》 2017年第1期217-218,共2页
Irradiation is one of the limited factors for all reactor materials alongside with high temperature,pressure and chemical interaction.The most profound effects of irradiation of materials occur in the core of nuclear ... Irradiation is one of the limited factors for all reactor materials alongside with high temperature,pressure and chemical interaction.The most profound effects of irradiation of materials occur in the core of nuclear reactors,where more aggressive environments,higher temperature and greater level of irradiation.A common parameter to evaluate the damage incurred in the structural materials by radiation is an integrated quantity known as displacements per atom(DPA),which allows comparing different sets of irradiation conditions.This measure is related to the number of the FPs.The DPA calculation requires to know neutron spectrum and flux under which the material is exposed and the material response,which can be described by displacement cross-section of the material.The displacement cross-section for 15-15Ti steel has been calculated by NJOY and IOTA codes. 展开更多
关键词 interaction. material. DISPLACEMENT
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