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JAEA Reports

Partitioning design study of large FBR; Diagram for thermal stress evaluation (Simplified analyses of discontinuity thermal stresses)

Furuhashi, Ichiro*; ; Imazu, Akira

PNC TN9410 87-158, 231 Pages, 1987/11

PNC-TN9410-87-158.pdf:11.0MB

Simplified analyses of discontinuity thermal stresses were performed using axisymmetrical shell theory for the purpose of saving cost and time of thermal stress calculations in the design of FBR's components. By these analyses, steady and unsteady thermal stresses are to be calculated easily and quickly for the following regions (1)edge of cylinder, (2)discontinuity of material properties and thickness, dissimilar metal pipe joint, (3)axial temperature distribution, cylinder near the liquid surface level, (4)junction of vessel & flange, (5)junction of nozzle and vessel, (6)skirt structures, nozzle safe end, and (7)ring reinforcement. Also, simple formulae were proposed for estimating thermal stresses caused by (9)circumferential temperature distribution of cylinder, (10)thermal striping near the structural wall. By using these results, one can easily evaluate thermal stresses for various shapes and dimensions, and saving of cost and time should be accomplished in the design of FBR's components.

JAEA Reports

Piping system of large FBRs on the IHX floating support concept; Vol.1 Analysis of the nozzles

; Furuhashi, Ichiro*; Imazu, Akira

PNC TN9410 87-094, 402 Pages, 1987/06

PNC-TN9410-87-094.pdf:63.97MB

This report describes flexibility, simplified stress calculation method and simple axisymmetrical modelling method for nozzles which were designed for large EBRs based on the IHX floating support concept. Stress analyses of nozzles were conducted with 3-dimensional solid model etc. under piping reaction force, internal pressure and thermal transient loadings by finite element FINAS code. The results of analyses are as follows; (1)Spring constants representing nozzle flexibility were prepared for piping analyses from the results of 3-dimensional shell analyses, (2)For internal pressure, an equivalent axial force was applicable in piping analyses, (3)Thermal transient loadings of 1 $$^{circ}$$C/sec temperature change caused higher stress than allowable limit, so more discussion is needed in thermal design of the FBRs, (4)Simplified stress calculation methods for each loading were developed, (5)Analytical modelling of 3-dimensional nozzle shapes to axisymmetrical shapes was developed for each loading.

JAEA Reports

Diagram for thermal stress evaluation; Vol.1 Theoretical analysis of thermal transient stress in the wall

; Furuhashi, Ichiro*; Imazu, Akira

PNC TN9410 87-028, 209 Pages, 1987/02

PNC-TN9410-87-028.pdf:38.14MB

The thermal stresses are generated in the walls of chemical plants, thermal power plants, and fast breeder reactors, etc. during start-up or shut-down of plants or during emergency shut-down. Parametric structural analyses will be required in the structural design of these plants to demonstrate that these thermal stresses are lower than allowable values. This report gives diagrams for calculating thermal stresses due to temperature distribution in wall thickness for various thermal parameters. We can get thermal stresses quickly by these diagrams without parameteric structural analyses. These diagrams can be most effectively applied for choosing the most desirable geometries at the initial stage of the design, even though they are not recommended to be used for the different types of thermal stresses caused by temperature distribution in axial direction of pipings and vessels.

JAEA Reports

Nuclear Parametric Study of the Pressure Tube-Type D$$_{2}$$O Moderated Lattices

Furuhashi, Akira;

JAERI 1080, 61 Pages, 1965/07

JAERI-1080.pdf:3.59MB

no abstracts in English

Journal Articles

Characteristic spectra in neutron thermalization, 2; The Effect of chemical binding

Furuhashi, Akira

Journal of Nuclear Science and Technology, 1(4), p.120 - 129, 1964/00

no abstracts in English

Journal Articles

Thermal neutron spectra in the two-region system

; Furuhashi, Akira

Nihon Genshiryoku Gakkai-Shi, 5(2), p.119 - 126, 1963/00

no abstracts in English

JAEA Reports

Critical experiments and analysis of homogeneous heavy water system; 20% enriched U-D$$_{2}$$O reflector

Hirota, Jitsuya; Kuroi, Hideo; Goto, Yorio; Furuhashi, Akira; Yasuno, Takehiko; Yamamoto, Ken; Mitani, Hiroshi; Obu, Makoto; Ichimori, Toshihiro; Koyama, Kinji; et al.

JAERI 1034, 50 Pages, 1962/08

JAERI-1034.pdf:3.64MB

no abstracts in English

Journal Articles

Characteristic spectra in neutron thermalization

Furuhashi, Akira

Nihon Genshiryoku Gakkai-Shi, 4(10), p.677 - 684, 1962/00

no abstracts in English

Journal Articles

On the analysis and interpretation of foil data

Furuhashi, Akira

Nihon Genshiryoku Gakkai-Shi, 4(11), p.797 - 807, 1962/00

no abstracts in English

JAEA Reports

Technical aspects of aqueous homogeneous reactor

Sugimoto, Asao; Takeda; Furuhashi, Akira; Katsuragi, Satoru; Hirota, Jitsuya; Naito, Keiji; Kondo, Yasuko; Nagasaki, Ryukichi; Yamazaki, Yasaburo; Kuroi, Hideo; et al.

JAERI 4018, 52 Pages, 1961/06

JAERI-4018.pdf:4.14MB

no abstracts in English

Journal Articles

Measuring the ratio of epithermal to thermal neutron densities using thick gold foils

Furuhashi, Akira; *;

Nihon Genshiryoku Gakkai-Shi, 2(7), P. 394, 1960/00

no abstracts in English

Journal Articles

Measurement of the thermal neutron diffusion length in thorium oxide and heavy water slurry

; Furuhashi, Akira; ; ; ;

Dai-3-Kai Genshiryoku Shimpojiumu Hobunshu, 1, P. 88, 1959/00

no abstracts in English

Journal Articles

On the $$beta$$-ray self-absorption crrection for the gold foil counting

Furuhashi, Akira;

Dai-3-Kai Genshiryoku Shimpojiumu Hobunshu, 2, P. 249, 1959/00

no abstracts in English

Journal Articles

Absolute measurement of the neutron flux

; Furuhashi, Akira

Dai-2-Kai Genshiryoku Shimpojiumu Hobunshu, P. 80, 1958/00

no abstracts in English

14 (Records 1-14 displayed on this page)
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