Proposal of simple model for investigating irradiation behavior of nuclear-grade graphite

Saijo, Tomoaki; Mizuta, Naoki; Hasegawa, Toshinari; Suganuma, Takuro; Shimazaki, Yosuke; Ishihara, Masahiro; Iigaki, Kazuhiko

JAEA-Technology 2024-002, 96 Pages, 2024/06

JAEA-Technology-2024-002.pdf:22.18MB

Nuclear-grade graphite is used for core components of High Temperature Engineering Test Reactor (HTTR) due to excellent heat resistant properties. The physical properties of this graphite change with temperature and neutron irradiation, as well as exhibit complex behavior such as irradiation deformation and creep deformation. Then, stress analysis code has been developed for the graphite. In previous study, the code has been used to evaluate the shutdown stress by residual strain that accumulates with neutron irradiation. However, the effects of change in physical properties such as Young's modulus and thermal expansion-coefficient on shutdown stress have not been fully understood. Therefore, an evaluation model based on a simplified beam model was developed to clarify the effects of changes in physical properties and complex deformations on stresses occurring during operation and reactor shutdown, and to contribute to the development of graphite structures with longer lifetimes. As an application example, the effects of changes on various physical properties on operational and shutdown stresses were clarified for graphite components in the temperature range from 600 to 800C.

Flexible and tough superelastic Co-Cr alloys for biomedical applications

Odaira, Takumi*; Xu, S.*; Hirata, Kenji*; Xu, X.*; Omori, Toshihiro*; Ueki, Kosuke*; Ueda, Kyosuke*; Narushima, Takayuki*; Nagasako, Makoto*; Harjo, S.; et al.

Advanced Materials, 34(27), p.2202305_1 - 2202305_11, 2022/07

https://doi.org/10.1002/adma.202202305

Development of a diagnostic technique using ultrasonic wave for evaluation of irradiation embrittlement in reactor pressure vessel materials

Ishii, Toshimitsu; Ooka, Norikazu; Hoshiya, Taiji; Kobayashi, Hideo*

KURRI-KR-62, p.29 - 41, 2001/03

no abstracts in English

Effect of thermal annealing on property changes of neutron-irradiated non-graphitized carbon materials and nuclear graphite

Matsuo, Hideto

JAERI-M 91-090, 15 Pages, 1991/06

JAERI-M-91-090.pdf:0.47MB

no abstracts in English

Study on radiation-resistant elastomer, 1; The Effect of anti-radiation additives on ethylene-propylene elastomer

Ito, Masayuki

Materiaru Raifu, 2(3), p.156 - 161, 1990/07

no abstracts in English

Irradiation creep properties of a near-isotropic graphite

; ;

Journal of Nuclear Materials, 152, p.225 - 234, 1988/00

https://doi.org/10.1016/0022-3115(88)90331-5

no abstracts in English

Irradiation Creep Properties of a Graphite for HTGRs

; ;

JAERI-M 86-120, 24 Pages, 1986/08

JAERI-M-86-120.pdf:0.8MB

no abstracts in English

Thermal Cycle Test of a Full-scale Graphite Sleeve for Use in the VHTR

JAERI-M 85-162, 18 Pages, 1985/10

JAERI-M-85-162.pdf:1.33MB

no abstracts in English

Neutron and -ray irradiation effects in composite organic insulators

; M.A.Kirk*; R.C.Birtcher*; Hagiwara, Miyuki

Journal of Nuclear Materials, 133-134, p.795 - 799, 1985/00

https://doi.org/10.1016/0022-3115(85)90260-0

no abstracts in English

Effect of heat treatment on physical properties of carbon material for use as thermal barrier in the VHTR(very high temperature gas-cooled reactor)

;

High Temperatures-High Pressures, 16, p.695 - 705, 1984/00

no abstracts in English