scholarly journals Influence of irradiation temperature on void swelling in NiCoFeCrMn and NiCoFeCrPd

2019 ◽  
Vol 158 ◽  
pp. 57-61 ◽  
Author(s):  
Tai-ni Yang ◽  
Chenyang Lu ◽  
Gihan Velisa ◽  
Ke Jin ◽  
Pengyuan Xiu ◽  
...  
Keyword(s):  
Irradiation Temperature ◽  
Void Swelling

Effect of irradiation temperature on void swelling of China Low Activation Martensitic steel (CLAM)

2008 ◽  
Vol 59 (3) ◽  
pp. 344-347 ◽  
Author(s):  
Fei Zhao ◽  
Jiansheng Qiao ◽  
Yina Huang ◽  
Farong Wan ◽  
Soumei Ohnuki
Keyword(s):  
Martensitic Steel ◽  
Irradiation Temperature ◽  
Void Swelling

Void Swelling Resistance in Fe-Cr Alloys at 200 DPA

1994 ◽  
Vol 373 ◽  
Author(s):  
D. S. Gelles
Keyword(s):  
Irradiation Temperature ◽  
The Other ◽  
Dislocation Network ◽  
Fast Breeder Reactor ◽  
Ferritic Alloys ◽  
Density Measurements ◽  
Void Swelling

AbstractMicrostructural examinations have been performed on a series of binary Fe-Cr alloys irradiated to 200 dpa at 425°C in a fast breeder reactor. The alloy compositions rangedfrom 3% to 18% Cr in 3% Cr increments, and the irradiation temperature corresponded to the peak swelling condition for this alloy class. Density measurements showed swelling levels as high as 7.4%, with the highest swelling found in the Fe-9Cr and Fe-6Cr alloys. Microstructural examinations revealed that the highest swelling conditions contained welldeveloped voids, often as large as 100 nm, and a dislocation network comprised of both a2 <111> and <100> Burgers vectors. Swelling was lower in the other alloys, and the swelling reduction could be correlated with increased precipitation. These results are considered in light of the current theories for low swelling in ferritic alloys, but no theory is available to completely explain the results.

The effect of radiation-induced segregation on void swelling in electron-irradiated austenitic Fe-Cr-Ni-Ti-P Alloy

1990 ◽  
Vol 48 (4) ◽  
pp. 932-933
Author(s):  
H. Watanabe ◽  
T. Muroga ◽  
N. Yoshida
Keyword(s):  
Temperature Dependence ◽  
Electron Irradiation ◽  
Irradiation Temperature ◽  
The Other ◽  
Austenitic Steels ◽  
Nickel Concentration ◽  
In Situ Observation ◽  
Void Swelling ◽  
Radiation Induced

It has been reported that the void swelling in austenitic steels at higher temperatures is enhanced by a nickel depletion in matrix . The objective of the present study is to understand the effect of solute addition on void swelling, in association with microchemical changes, in austenitic steels during electron irradiation.Four types of model alloys (Fe-16Cr-17Ni, Fe-16Cr-17Ni-0.25Ti, Fe- 16Cr-17Ni-0.1P, Fe-16Cr-17Ni-0.25Ti-0.IP) and JPCA-2 were used in this study. Irradiation and in-situ observation were carried out with 1.0 MeV electrons utilizing JEM-1000 of HVEM Lab. Kyushu Univ.Fig. 1 shows the irradiation temperature dependence of nickel concentration in matrix after irradiated at 2 dpa. The ternary alloy and alloys containing phosphorus(or titanium) only show a strong nickel depletion in matrix due to nickel segregation to defect sinks. Our previous results about void swelling in these alloys showed that the temperature, where nickel depletion in matrix became prominent, corresponded to that of maxium void swelling. On the other hand, void swelling and the nickel depletion were not detected in Fe-16Cr-17Ni-0.25Ti-0.IP and JPCA-2.

Swelling Characteristics of a Type 304SS Baffle Plate Irradiated up to 50 DPA in PWR and Validation of a Swelling Equation

2017 ◽  
Author(s):  
Yuichi Mogami ◽  
Toru Matsubara ◽  
Seiji Yaguchi ◽  
Tomohiro Tsuda ◽  
Koji Fujimoto
Keyword(s):  
Structural Integrity ◽  
Irradiation Temperature ◽  
Baffle Plate ◽  
Pressurized Water ◽  
Volumetric Expansion ◽  
Void Swelling ◽  
Swelling Characteristics ◽  
Similar Temperature ◽  
Water Reactors ◽  
Reactor Internals

When austenitic stainless steel is highly irradiated in a reactor under high temperature, voids will be created in the material, leading to volumetric expansion of structures. This phenomenon is known as void swelling. The deformation caused by the swelling possibly deteriorates the functionality of reactor internals in Pressurized Water Reactors (PWRs), especially baffle former assemblies. To evaluate the functionality of the internals against the swelling and to assure the structural integrity, simulation technologies play a key role, enabling the estimation of the swelling behavior of the internals through plant life. The simulation results strongly depend on inputs, especially on a swelling equation; however, it includes uncertainty to some extent because quite limited swelling data in PWR environment have been available, which are necessary for the validation of the equation. To enable the validation of swelling equations and improve the reliability on the simulations, the authors investigated the swelling characteristics of a type 304SS baffle plate removed from a decommissioned PWR plant. A total of nine swelling data were obtained with the variety in neutron dose (33 to 47 dpa) and irradiation temperature (299 to 327°C). The swelling ratios obtained are ranging from 0.02 to 0.08%, which corresponds well with the swelling equation, showing the similar temperature dependency with the equation. Since the irradiation temperature range of the obtained data, up to 327°C, covers major part of baffle former assemblies, swelling ratios of most part of them are expected to be small, which is probably too small to harm the functionality of the assemblies. The results contribute to the better confidence on swelling simulations and to assure the integrity of PWR reactor internals.

Voids in Irradiated Tungsten and Molybdenum

1969 ◽  
Vol 27 ◽  
pp. 190-191
Author(s):  
Robert C. Rau ◽  
Robert L. Ladd
Keyword(s):  
Melting Point ◽  
Fast Neutron ◽  
Neutron Irradiation ◽  
Elevated Temperatures ◽  
Irradiation Temperature ◽  
The Body ◽  
Face Centered Cubic ◽  
Body Centered Cubic ◽  
Cubic Metals ◽  
Face Centered

Recent studies have shown the presence of voids in several face-centered cubic metals after neutron irradiation at elevated temperatures. These voids were found when the irradiation temperature was above 0.3 Tm where Tm is the absolute melting point, and were ascribed to the agglomeration of lattice vacancies resulting from fast neutron generated displacement cascades. The present paper reports the existence of similar voids in the body-centered cubic metals tungsten and molybdenum.

Effect of irradiation temperature on the radiolysis of methane

1981 ◽  
Vol 17 (3) ◽  
pp. 151-157 ◽  
Author(s):  
H. Arai ◽  
S. Nagai ◽  
K. Matsuda ◽  
M. Hatada
Keyword(s):  
Irradiation Temperature

scholarly journals Irradiation Hardening Behavior of He-Irradiated V–Cr–Ti Alloys with Low Ti Addition

2020 ◽  
Vol 5 (1) ◽  
pp. 1
Author(s):  
Ken-ichi Fukumoto ◽  
Yoshiki Kitamura ◽  
Shuichiro Miura ◽  
Kouji Fujita ◽  
Ryoya Ishigami ◽  
...  
Keyword(s):  
Ion Irradiation ◽  
Optimum Composition ◽  
Solid Solution Hardening ◽  
Irradiation Hardening ◽  
Hardening Behavior ◽  
Ti Alloys ◽  
Void Swelling ◽  
Before And After ◽  
Cr Addition ◽  
Ti Addition

A set of V–(4–8)Cr–(0–4)Ti alloys was fabricated to survey an optimum composition to reduce the radioactivity of V–Cr–Ti alloys. These alloys were subjected to nano-indenter tests before and after 2-MeV He-ion irradiation at 500 °C and 700 °C with 0.5 dpa at peak damage to investigate the effect of Cr and Ti addition and gas impurities for irradiation hardening behavior in V–Cr–Ti alloys. Cr and Ti addition to V–Cr–Ti alloys for solid–solution hardening remains small in the unirradiated V–(4–8)Cr–(0–4)Ti alloys. Irradiation hardening occurred for all V–Cr–Ti alloys. The V–4Cr–1Ti alloy shows the highest irradiation hardening among all V–Cr–Ti alloys and the gas impurity was enhanced to increase the irradiation hardening. These results may arise from the formation of Ti(CON) precipitate that was produced by He-ion irradiation. Irradiation hardening of V–Cr–1Ti did not depend significantly on Cr addition. Consequently, for irradiation hardening and void-swelling suppression, the optimum composition of V–Cr–Ti alloys for structural materials of fusion reactor engineering is proposed to be a highly purified V–(6–8)Cr–2Ti alloy.

Effects of irradiation temperature on tritium retention in stainless steel type 316L

2021 ◽  
Vol 169 ◽  
pp. 112436
Author(s):  
Masao Matsuyama ◽  
Hideki Zushi ◽  
Kazuaki Hanada ◽  
Yasuhisa Oya ◽  
Yuji Hatano
Keyword(s):  
Stainless Steel ◽  
Irradiation Temperature ◽  
Steel Type ◽  
Type 316L

Cascade damage effects on the swelling of irradiated materials

1975 ◽  
Vol 346 (1644) ◽  
pp. 81-102 ◽  
Keyword(s):  
Neutron Irradiation ◽  
Elevated Temperatures ◽  
Heavy Ion ◽  
Rate Theory ◽  
Void Swelling ◽  
Solution Treated ◽  
Continuous Generation ◽  
Volume Swelling ◽  
Physical Features ◽  
Cascade Damage

The homogeneous rate theory of void growth is extended to include the possibility of forming vacancy loops when the irradiation produces cascade damage. The analysis provides a basis for understanding and correlating the relative swelling generated during electron; heavy ion and fast neutron irradiation. In order to illustrate the physical features of the model it is applied in some detail to calculating the volume swelling in solution treated M316 stainless steel for which there is a considerable amount of experimental data. The results from these calculations serve to expose the sensitivity of void swelling to the scale on which interstitial loops are nucleated. They also highlight the particular difficulty arising from the continuous generation of transmutation gas in predicting swelling under neutron irradiation at elevated temperatures.

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