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JAEA Reports

The Development of fuel pins and material specimens mixed loading irradiation test rig in the experimental fast reactor Joyo; The Development of the fuel-material hybrid rig

Oyamatsu, Yasuko*; Someya, Hiroyuki

JAEA-Technology 2012-046, 80 Pages, 2013/02

JAEA-Technology-2012-046.pdf:5.43MB

In the experimental fast reactor Joyo, there were many tests using the irradiation rigs that it was possible to be set irradiation conditions for each compartment independently. In case of no alternative fuel element to irradiate after unloading the irradiated compartments, the irradiation test was restarted with the dummy compartment which the fuel elements was not mounted. If the material specimens are mounted in this space, it is possible to realize effective utilization of the irradiation space. For these reasons, the irradiation rig (hybrid rig) consolidated with fuel elements and material specimens are developed. Fuel elements and material specimens differ greatly with heat generation, so that the point for developing of hybrid rig is being able to distribute appropriately the coolant flow which satisfies irradiation conditions. The following is described by this report. (1) It was confirmed that the flow distribution of loading the same irradiation rig with the compartment from which a flow demand differs could be satisfied. (2) It was confirmed that temperature setting capability equivalent to the former was securable. (3) By standardizing the coolant entrance structure of the compartment lower part, the prospect which can perform easily recombination of the compartment from which a kind differs between irradiation rigs was acquired.

Journal Articles

Estimation for temperature distribution in a heat-generating cylinder with multiple holes

; Hoshiya, Taiji; ; Niimi, Motoji; *

Journal of Nuclear Science and Technology, 30(4), p.291 - 301, 1993/04

 Times Cited Count:4 Percentile:44.86(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

SATCAP-C: A Program for thermal hydraulic design of pressurized water injection type capsule

; ; Aso, Tomokazu; Niimi, Motoji

JAERI-M 92-149, 78 Pages, 1992/10

JAERI-M-92-149.pdf:2.53MB

no abstracts in English

Journal Articles

Effect of eccentric pellet on gap conductance in fuel rod

; ; Hoshiya, Taiji

Journal of Nuclear Science and Technology, 28(10), p.961 - 964, 1991/10

no abstracts in English

JAEA Reports

Design procedure of capsule with multistage heater control, named MUSTAC

; Endo, Yasuichi; Hoshiya, Taiji; Niimi, Motoji;

JAERI-M 90-214, 57 Pages, 1990/11

JAERI-M-90-214.pdf:1.59MB

no abstracts in English

JAEA Reports

JAEA Reports

SATCAP-B; A Program for thermal-hydraulic design of saturated temperature capsule

; ; Niimi, Motoji

JAERI-M 89-187, 60 Pages, 1989/11

JAERI-M-89-187.pdf:1.63MB

no abstracts in English

JAEA Reports

Thermal characteristic test for saturated temperature type capsule

Niimi, Motoji; ; *; ;

JAERI-M 89-099, 30 Pages, 1989/08

JAERI-M-89-099.pdf:0.78MB

no abstracts in English

JAEA Reports

CAPSTAR: A program to evaluate safety strength for outer/inner tubes of capsules

*; Hoshiya, Taiji; Niimi, Motoji; ;

JAERI-M 88-121, 36 Pages, 1988/07

JAERI-M-88-121.pdf:0.78MB

no abstracts in English

JAEA Reports

SATCAP; A program for thermal-hydraulic design of saturated temperature capsule

; *; Niimi, Motoji;

JAERI-M 88-013, 49 Pages, 1988/02

JAERI-M-88-013.pdf:1.3MB

no abstracts in English

JAEA Reports

GENGTC-JB: A computer program to calculate temperature distribution for cylindrical geometry capsule

; *; Niimi, Motoji; Hoshiya, Taiji;

JAERI-M 87-148, 25 Pages, 1987/09

JAERI-M-87-148.pdf:0.69MB

no abstracts in English

Oral presentation

Future direction of material irradiation test service in the experimental fast reactor Joyo

Soga, Tomonori; Itagaki, Wataru; Someya, Hiroyuki; Yamamoto, Masaya; Tobita, Koichi

no journal, , 

Oral presentation

Technology succession through assembling the dummy fuel assembly at the Irradiation Rig Assembling Facility (IRAF)

Itagaki, Wataru; Noguchi, Koichi; Endo, Norio; Nakamura, Toshiyuki; Ashida, Takashi; Saito, Takakazu; Someya, Hiroyuki*; Tomine, Hiroshi*; Kato, Jun*; Gunji, Masakatsu*

no journal, , 

no abstracts in English

Oral presentation

Current status of application to meet new regulations and expansion of irradiation capabilities after restart

Saito, Hiroto; Yamamoto, Masaya; Someya, Hiroyuki*; Itagaki, Wataru; Maeda, Shigetaka; Takamatsu, Misao

no journal, , 

Toward restart, the experimental fast reactor Joyo is now under the safety review by regulatory body. After restart, we would like to play a enhanced role of fast neutron irradiation experiments. In order to discuss with irradiation materials researchers, introduce the irradiation capabilities of Joyo after restart.

Oral presentation

Material irradiation technique in Joyo and progress of regulator's safety screening

Itagaki, Wataru; Saito, Hiroto; Someya, Hiroyuki*; Yano, Yasuhide; Otsuka, Satoshi; Takamatsu, Misao; Maeda, Shigetaka; Sekine, Takashi

no journal, , 

no abstracts in English

17 (Records 1-17 displayed on this page)
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