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JAEA Reports

Investigation of the properties of high temperature resistance alloys used in the helium gas cooled high temperature reactor

Uwaba, Tomoyuki

JNC-TN9420 2000-005, 28 Pages, 2000/03

JNC-TN9420-2000-005.pdf:0.94MB

In the first phase of the feasibility study, their basic objectives are presentating the feasible image and scenario of development of the FBR cycle system, which is composed of the fast reactor, spent fuel reprocessing and fuel manufacturing facility. In the development of the FBR system in this phase, various ideas of plants are to be studied, which include coolant types such as sodium, heavy metals, gases(CO$$_{2}$$, He), wator, and middle or small size of the reactor, and fuel types (MOX, metal and nitride). In this report, as a part of this study, materials used for the core of the helium gas cooled reactor and their integrity (corrosion, mechanical and irradiation property) under high temperature helium atmosphere were investigated from open literatures.

JAEA Reports

lnvestigation for corrosion behavior of ferritic core materials in C0$$_{2}$$ gas cooled reactor

; ; Mizuta, Shunji

JNC-TN9400 2000-040, 41 Pages, 2000/03

JNC-TN9400-2000-040.pdf:0.85MB

The corrosion behavior of ferritic stainless steels applied to core components under C0$$_{2}$$ gas environment was investigated in order to be helpful to fuel design in C0$$_{2}$$ gas cooled reactor as the feasibility study for fast breeder reactor. The dependence of the corrosion behavior, before a breakaway occurs, on C0$$_{2}$$ gas temperature, Si and Cr contents of ferritic steels was determined quantitatively. The following correlations to calculate the metal loss thickness was established. X = 4.4w w = √(k$$times$$t) k = $$alpha$$ $$times$$ exp( - 5.45[Si]) $$times$$ exp( - 1.09[Cr]) $$times$$ exp( - 11253/T) $$alpha$$ = 1.65 $$times$$ 10$$^{8}$$$$sim$$4.40 $$times$$ 10$$^{9}$$ X : metal loss thickness[$$mu$$ml, w : corrosion weight gain [mg/cm$$^{2}$$] k : parabola constant [(mg/cm$$^{2}$$)$$^{2}$$/hr], t : time [hr], $$alpha$$ : constant [Si] : Si content[wt.%], [Cr] : Cr content [wt.%], T : temperature [K]

JAEA Reports

Study on improvement of reactor physics analysis method for FBRs with various core concept

*; Kitada, Takanori*; Tagawa, Akihiro*; *; Takeda, Toshikazu*

JNC-TJ9400 2000-006, 272 Pages, 2000/02

JNC-TJ9400-2000-006.pdf:9.69MB

Investigation was made on the follwing three themes as a part of the improvement of reactor physics analysis method for FBR with various core concept. Part 1: Investigation of Error Estimation of Neutron Spectra in FBR and Suggestions to Improve the Accuracy. In order to improve the spectrum unfolding method used in fast experimental reactor JOYO, a trial was made to evaluate the error in the estimated neutron spectrum, cause by cause. And the evaluated errors were summed up to obtain the most probable and reasonable error as possible. The summed up error was found relatively small compared to the error caused by the uncertainty of cross section data: most of the error in the spectrum unfolding method can be attributed to the error in cross sections. It was also found that the error due to the fission spectrum causes a considerable error in the high energy neutron spectrum which is over several MeV. Part 2: Study on Reactor Physics Analysis Method for Gas-Cooled FBR. In gas-cooled FBR, the portion of coolant channels in core volume is larger than sodium-cooled FBR. This leads to strong neutron streaming effects. For sodium-cooled FBR, several methods were proposed to evaluate the neutron streaming effect, however, these methods can not be used directly to gas-cooled reactor because the direction dependent diffusion coefficient becomes infinitive along the direction pararel to the coolant chammel. In this study, a new method is proposed to evaluate the neutron streaming effect, based on the method taking the axial buckling into consideration, which method was originally proposed by K$"o$hler. Part 3: Study on Reactor Physics Analysis Method for Water-Cooled FBR An investigation was made on low-moderated water-cooled FBR, on the point that the ordinary used analysis method for FBR may give considerable difference in results in such core. In light water reactors, it is well known that the space dependence of self-shielding effect of heavy nuclides are considerably ...

JAEA Reports

A Study on shaft vibration of gas circulators with gas-bearing for HENDEL test facility

Shimomura, Hiroaki; Kawaji, Satoshi; Fujisaki, Katsuo;

JAERI-M 89-064, 90 Pages, 1989/06

JAERI-M-89-064.pdf:3.71MB

no abstracts in English

Journal Articles

Mass transfer of mixed gas flow crossing a high temperature graphite cylinder with chemical reactions and in-pore diffusion

Ogawa, Masuro

Int.J.Heat Mass Transfer, 30(5), p.1017 - 1026, 1987/05

 Times Cited Count:5 Percentile:44.78

no abstracts in English

Journal Articles

Mass transfer of mixed gas flow crossing a high temperature porous cylinder with chemical reactions and in-pore diffusion.

Ogawa, Masuro

Nippon Kikai Gakkai Rombunshu, B, 53(488), p.1351 - 1359, 1987/00

no abstracts in English

JAEA Reports

Inclining Test in Bottom-Core Structure

;

JAERI-M 85-054, 16 Pages, 1985/04

JAERI-M-85-054.pdf:0.8MB

no abstracts in English

Journal Articles

Dimensional change of carbon material under compressive stress at high temperatures

; ;

High Temperatures-High Pressures, 15, p.707 - 714, 1983/00

no abstracts in English

JAEA Reports

Journal Articles

Experiments on the reduction of hydrogen permeation, 1; Liquid-metal-inbetween method

Sanokawa, Konomo; Ouchi, Mitsuo;

Nippon Genshiryoku Gakkai-Shi, 22(2), p.121 - 128, 1980/00

 Times Cited Count:0 Percentile:100(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Experiments on the reduction of hydrogen permeation, 2; Calorizing method

; Sanokawa, Konomo; Ouchi, Mitsuo; Takizuka, Takakazu; Nekoya, Shinichi; Ogawa, Masuro; Emori, Kouichi

Nippon Genshiryoku Gakkai-Shi, 22(4), p.251 - 263, 1980/00

 Times Cited Count:3 Percentile:57.27(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Construction and performance of a hydrogen secondary cooling system, 1; Facility and performance of the components

; Nekoya, Shinichi; Emori, Kouichi; Ogawa, Masuro; Ouchi, Mitsuo; ; Sanokawa, Konomo; *; *; *; et al.

Nippon Genshiryoku Gakkai-Shi, 22(3), p.181 - 188, 1980/00

 Times Cited Count:0 Percentile:100(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

JAEA Reports

JAEA Reports

A Review on the Production of Hydrogen from Water Using Nuclear Energy

; Tagawa, Hiroaki; ; ; Ono, Shinichi;

JAERI-M 5642, 69 Pages, 1974/03

JAERI-M-5642.pdf:2.49MB

no abstracts in English

JAEA Reports

General Description of High Temperature Gas Loop

; Sanokawa, Konomo; ; ; Akino, Norio;

JAERI-M 5152, 17 Pages, 1973/03

JAERI-M-5152.pdf:0.73MB

no abstracts in English

Journal Articles

Journal Articles

Recent Development of coated particle fuel for high temp.gas cooled reactor

Nihon Kinzoku Gakkai Kaiho, 12(3), p.181 - 187, 1973/03

no abstracts in English

Journal Articles

The test equipment for OGL-1 helium gas purification system

*; *; ; *

FAPIG, (69), p.2 - 7, 1973/00

no abstracts in English

Journal Articles

Some Aspects on Heat Transfer and Fluid Dynamics of High Temperature Gas Cooled Reactor

;

Nippon Genshiryoku Gakkai-Shi, 13(8), p.456 - 461, 1972/00

no abstracts in English

26 (Records 1-20 displayed on this page)