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JAEA Reports

None

Mitsugi, Takeshi; Yamanouchi, Sadamu; Tachibana, Toshimichi

PNC TN9410 87-197, 36 Pages, 1987/03

PNC-TN9410-87-197.pdf:2.12MB

None

JAEA Reports

None

Namekawa, Takashi; Yamanouchi, Sadamu; Tachibana, Toshimichi; *; *; *; *

PNC TN9410 87-198, 78 Pages, 1987/02

PNC-TN9410-87-198.pdf:10.49MB

None

JAEA Reports

None

Mitsugi, Takeshi; Yamanouchi, Sadamu; Tachibana, Toshimichi; Namekawa, Takashi; *; *; *

PNC TN9410 87-196, 64 Pages, 1987/02

PNC-TN9410-87-196.pdf:3.56MB

None

JAEA Reports

None

*; Tachibana, Toshimichi; Yamanouchi, Sadamu

PNC TN9410 87-195, 28 Pages, 1987/02

PNC-TN9410-87-195.pdf:1.46MB

None

JAEA Reports

None

Namekawa, Takashi; Tachibana, Toshimichi; Yamanouchi, Sadamu; *; *; *; Mitsugi, Takeshi

PNC TN9410 87-190, 103 Pages, 1987/02

PNC-TN9410-87-190.pdf:7.35MB

None

JAEA Reports

None

Namekawa, Takashi; Yamanouchi, Sadamu; Tachibana, Toshimichi

PNC TN9410 86-148, 52 Pages, 1986/11

PNC-TN9410-86-148.pdf:9.99MB

None

JAEA Reports

None

Namekawa, Takashi; Tachibana, Toshimichi; Yamanouchi, Sadamu

PNC TN9410 86-133, 22 Pages, 1986/01

PNC-TN9410-86-133.pdf:1.45MB

None

Journal Articles

None

Itaki, Toshiyuki; ; Yamanouchi, Sadamu; *; Shibahara, Itaru; *

Nihon Genshiryoku Gakkai-Shi, 27(5), p.435 - 449, 1985/05

 Times Cited Count:4 Percentile:54.95(Nuclear Science & Technology)

None

JAEA Reports

Postirradiation examination of JOYO MK-I core fuel PPJX13; Destructive examination of fuel elements

Yamanouchi, Sadamu; Kuwajima, Y.; Namekawa, Takashi; Inui, T.; Kondo, M.; Tani, Y.; Usui, Keiji; Nagai, Shuichiro

PNC TN9410 85-138, 109 Pages, 1985/03

PNC-TN9410-85-138.pdf:7.0MB

The JOYO MK-I core fuel subassembly PPJX13 was irradiated in JOYO MK-I core (location; 000) from 50 MW test through 75 MW 6th cycle. The average burnup was about 40,100 MWD/MTM. Five fuel pins was selected in the subassembly. Destructive examination items were metallographic examination (fuel and cladding), micro-hardness measurement, cladding density measurement and burnup measurement. The following results were obtained; (1) Central void of about 250Mm$$phi$$, columner grain region, equiaxed region (gas bubble region) and densified equiaxed region was formed by fuel restrusting. (2) Fuel and Cladding residual gap width were 20 $$mu$$m $$sim$$ 89 $$mu$$m. Fuel-cladding chemical interaction was 13 $$mu$$m at the maximum cladding temperature. (3) Carbide precipitation along the grain boundary and twinning zone were observed at high temperature position in cladding. Cladding micro-hardness indicated high value at low temperature position. (4) The cladding density change of 1.10% were observed in R material. (5) Burnup measurement by $$^{148}$$Nd isotope analysis using mass spectrometer showed 5.22 atom % at the center position of the center fuel pin.

JAEA Reports

Post irradiation examination of JOYO MK-I blanket fuel (NFJI11, NFJO4K, NFJO64, and NFJO5L); Destructive examination of fuel elements

Namekawa, Takashi; *; Yamanouchi, Sadamu

PNC TN9410 85-137, 72 Pages, 1985/03

PNC-TN9410-85-137.pdf:8.12MB

The JOYO MK-I blanket fuel subassemblies; NFJI11, NFJO4K, NFJO64, and NFJO5L were irradiated in the core location of 5D1, 6D1, 7D1, and 8D1 respectively. One of four subassemblies NFJI11 was irradiated from the 50MW 1st cycle to the end cycle of MK-I core, and the others from the 50MW low power test to the end cycle. One or two fuel pins were selected from each subassembly and the destructive postirradiation examinations that were metallographic examination and burnup measurement, were performed in AGF. The following results were obtained; (1)Fuel restructurings were not found for all subassemblies under microstructure observation. (2)FCCI was not observed for all subassemblies. (3)Axial distribution of normalized measured burnups had a good agreement with calculated profile by JYHIST code for all subassemblies. (4)Radial distribution curve of measured burnups toward the core center had more gentle slope than the calculated one. (5)Plutonium content which was generated by the neutron capture of U-238, varied with burnup, and the distribution curve had more gentle slope than the burnup curve.

Journal Articles

Determination of Melting Point of Mixed-Oxide Fuel Irradiated in Fast Breeder Reactor

Tachibana, Toshimichi; Itaki, Toshiyuki; Yamanouchi, Sadamu; Omori, Tsuyoshi*

Journal of Nuclear Science and Technology, 22(2), p.155 - 157, 1985/00

 Times Cited Count:19 Percentile:93.02(Nuclear Science & Technology)

None

Journal Articles

Development of a New Measurement Method for Fast Breeder Reactor Fuel Burnup Using a Shielded lon Microprobe Analyzer

Mizuno, Mino*; Enokido, Yuji; Unno, Ichiro; Kono, Kenichi; Yamanouchi, Sadamu; Itaki, Toshiyuki

Nuclear Technology, 69(1), p.107 - 113, 1985/00

 Times Cited Count:0 Percentile:0.02(Nuclear Science & Technology)

None

JAEA Reports

Report on result of special test of fast experimental reactor "JOYO"; Isothermal reactivity coefficient and flow rate reactivity coefficient

*; *; Yamanouchi, Sadamu; *; Enokido, Yuji*; Shibahara, Itaru*; *

PNC TN941 82-38, 57 Pages, 1982/02

PNC-TN941-82-38.pdf:2.35MB

The isothermal reactivity coefficient and the flow rate reactivity coefficient of the Fast Breeder Reactor "JOYO" were measured during the power ascension test of 50MW. After 4 years operation, the core configuration of "JOYO" was increased to 79 from 70 subassemblies. The present experiment was intended to search the age effect for the above reactivity coefficients. The results obtained were as follows. [Isothermal reactivity coefficient] (1)The present value measured ((-3.85$$pm$$0.17)$$times$$10$$^{-3}$$% $$delta$$k/k/$$^{circ}$$C) shows good agreement with the design value and the value measured previously. (2)The age effect and the effect caused by the anomaly of the power reactivity coefficient are not found. [Coolant flow rate reactivity coefficient] (1)The reactivity change caused by changing of the flow rates in primary sodium loop (100% to 20%) was (-8.2$$sim$$-10.7) $$times$$ 10$$^{-3}$$%$$Delta$$k/k. This value is about 1/10 of the design value and 1/3 of the measured value before the 75 MW power ascension test. (2)The detailed analysis is needed to search the relation between the anomaly of the power reactivity coefficient and the above change of this coefficient.

JAEA Reports

Irradiation Test Shielding Material for Fast Reactor JMTR-SH (I) (71M-84P)

Suzuki, Kazuhisa; Yamanouchi, Sadamu; Tani, Satoshi; Ichige, Akio; Naito, Takeshi; Harada, Mamoru; Ito, Masahiko; Osugi, Shoichi*; Shibata, Kenichi*

PNC TN951 76-05, 70 Pages, 1976/03

PNC-TN951-76-05.pdf:4.32MB

The serpentine concentrate in which two kinds of cement were used as a binder was irradiated in JMTR to the fast neutron fluence -1.7$$times$$$$^{19}$$ n/cm$$^{2}$$ (E$$>$$1Mev) and thermal neutron fluence -1.5$$times$$10$$^{20}$$ n/cm$$^{2}$$. Ave-rage irradiation temperature was estimated to be 200$$^{circ}C$$. Prior to the postirradiation examination, effect of thermal history was investi- gated in out-of-pile test.The integrity of specimens were kept after irradiation. From the results of thermal history examination and the post-irradiation examination, it was clearly noticed that the changes occuring in dimensions, weight and compressive strength were caused mainly by the thermal effect. The change in the Young's modulus seemed to be caused by the effect of both heating and neutron irradiation. It wasconcluded that the ordinary portland cement with the serpentine concrete is better than that of almina cement.

14 (Records 1-14 displayed on this page)
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