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Itaki, Toshiyuki; ; Yamanouchi, Sadamu; ; Shibahara, Itaru;
Nihon Genshiryoku Gakkai-Shi, 27(5), p.435 - 449, 1985/05
Times Cited Count：4 Percentile：54.51(Nuclear Science & Technology)None
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：92.69(Nuclear Science & Technology)None
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
; ; Yamanouchi, Sadamu; ; Enokido, Yuji*; Shibahara, Itaru*;
PNC TN941 82-38, 57 Pages, 1982/02
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
0.17)
10
% 
k/k/
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
-10.7) 10%
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.
Koizumi, Masumichi; ; ; ; Furuya, Hirotaka
PNC TN841 76-33, 72 Pages, 1976/10
no abstracts in English
; Akutsu, Hideo*; ; Miyahara, Kenji; ;
PNC TN841 75-34, 23 Pages, 1975/09
Non-destructive assay equipment for quantitative determination of the neuclear material in plutonium fuel fabrication facility. In plutonium fuel Fabrication Facility (PFFF) of PNC, nuclear materials are received in the form of oxide powder both for plutonium and uranium as raw material, and are shipped to reactor site as the sub-assembly after passing through fabrication processes such as pellet preparation, fuel rod fabrication and assembling. This production line has some strategic points where the nondestructive assay is available for the safeguards techniques. In our facility, four strategic points for nondestructive assay were established as follows. (1) Receiving of nuclear material, (2) Shipping of subassembly, (3) Fuel rod, (4) Contaminated waste and scrap of the fuel power or pellets. This paper reports the result obtained from a callorimeter, 
scanner, neutron coincidence meter that was prepared for these strategic points.
Akutsu, Hideo*; Koizumi, Masumichi; Kashima, Sadamitsu;
PNC TN841 75-15, 55 Pages, 1975/04
This document is completed according to the quality control and testing procedures described in "Preliminary Design of PNC-5 Subassembly for Rapsodie Irradiation" Coprecipilation methods was employed for preparing PuO
-UO powder. Five lots of pellets are provided for fablication of forty fuel pins. Fablication process of PuO$_{2-UO$_{2 powder, pellets and fuel pins are shown in Fig.3-1, Fig.3-2, Fig.3-3 respectively.
; ; Itaki, Toshiyuki; ; ; Komatsu, Junji
Inter.Conf.on Reliable Fuels for Liquid Metal Reactores, ,
None
Shibahara, Itaru; ; ; Itaki, Toshiyuki
International Conference on Materials for Nuclear Reactor Core Applications, ,
None
