JOPSS - Search Results

To develop a ceramic liner, a selection test of materials, an improvement test of selected material, and a feasibility test of the liner have been conducted.in the selection test, fifty commercially available high temperature cement and ceramics were subjected to thermal shock test (tst), sodium exposure test(set), and sodium flame exposure test (sfet). From test results, alumina/silicon-carbide (Al $_{2}$ O $_{3}$ -sic)mixture base castable refractory was selected in consideration of material cost, and material availability for a simpler liner construction in the buildings. The selected material was subjected to the improvement test. from the test, proper weight fractions of additives such as alumina cement and silica were determined. Drying conditions were also determined. Finally, a sodium burning pan made of concrete whose inner surfaces were covered with the improved Al $_{2}$ O $_{3}$ -sic base castable refractory was fabricated and was used for a sodium burning test.

Journal Articles

Thermal shock testing of low-z coatings for JT-60

; ; ; Murakami, Yoshio

Journal of Nuclear Materials, 111-112, p.852 - 855, 1982/00

https://doi.org/10.1016/0022-3115(82)90319-1

Times Cited Count：15 Percentile：80.73(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

Safety Evaluation of Simulated High-Level Waste Glass Products,III; Drop Impact Test of Products

; ; *; ; *; ; ; *; ; Araki, Kunio

JAERI-M 9191, 18 Pages, 1980/11

JAERI-M-9191.pdf:1.11MB

no abstracts in English

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Bayesian uncertainty evaluation of Charpy ductile-to-brittle transition temperature for reactor pressure vessel steels

Mechanical property of F82H steel doped with boron and nitrogen

Evaluation of neutron irradiation embrittlement in structural materials for reactor pressure vessel

Comparison of transition temperature shifts between static fracture toughness and Charpy-V impact properties due to irradiation and post-irradiation annealing for Japanese A533B-1 steels

Disruption erosion tests on La $_{2}$ O $_{3}$ containing tungsten material

Properties of precipitation hardened steel irradiated at 323K in the Japan Materials Testing Reactor

Thermal shock test of neutron irradiated carbon fiber reinforced carbon composites with OHBIS

Development of reconstitution technique of irradiated speciments, 3; Report for FY 1995 and FY 1996 on JAERI-IHI cooperated research program (Joint research)

Disruption and erosion on plasma facing materials with Oarai hot-cell electron beam irradiating system (OHBIS)

Shape memory characteristics of neutron irradiated Ti-Ni shape memory alloy couplers

Development of reconstitution method for surveillance specimens using surface-activated joining

Development of reconstitution technique of irradiated specimen, II; Annual report for FY1994 on JAERI-IHI cooperated research program

Application of solid state diffusion bonding to fusion reactor

Surface-activated joining,reconstitution technique of surveillance specimens

Fracture behavior of nuclear graphites under tensile impact loading

High temperature thermomechanical characterization by thermal shock tests on C/C composites for nuclear applications

Thermal fracture stresses of isotropic graphite

Development of ceramic liner for FBR building

Thermal shock testing of low-z coatings for JT-60

Safety Evaluation of Simulated High-Level Waste Glass Products,III; Drop Impact Test of Products