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Yutani, Toshiaki*; Wada, Takashi*; Matsuzuka, Ryuji*; Yamanaka,Tsuneyasu*; Watari, Yoshio*
PNC TJ9124 87-007, 43 Pages, 1987/09
To evaluate the corrosion resistance due to fuel-cladding chemical interaction (FCCI), corrosion tests of an advanced austenitic stainless steel of French manufacture and modified SUS316 stainless steel fabricated by air melting method and doble vacuum melting method with CsOH-CsI mixture, tellurium and iodine were conducted at 700
C for 100 hours. The result were summarized as follows. (1)The CsOH-CsI mixture (CsOH-CsI=1) produced intergranular attack, (2)Tellurium and iodine produced matrix attack. (3)There were little difference in corrosion morphology between three alloys. (4)Advanced austenitic stainless steel and modified SUS316 stainless steel farbricated by air melting method had almost same corrosion resistances to CsOH-CsI mixtures and iodine as modified SUS316 stainless steel farbricated by double vacuum melting method.
Watari, Yoshio*; *; *
PNC TJ902 84-05, 168 Pages, 1984/08
The Analysis on the Gamma heating of the 0'th cycle of "Joyo" MK-II Core has been performed. In advance of this analysis, the followings have been performed. (1)The Cross Sections for the Gamma heating analysis have been prepared based on JENDL-IIB-70 and the second Gamma production data which was made from ENDF-B/IV. These Cross Sections include the Neutron Cross Section, the second Gamma production Cross Section and the Gamma transport cross section. The number of the energy groups is 7 for the Neutron, and 20 for the Gamma ray. (2)The analysis on the experiment of the Gamma heating in the FCA X-2. This FCA X-2 is the mock-up of the "Joyo" MK-II core. The analysis has been performed based on the RZ-geometry and the XY-geometry. The Gamma source was calculated with the Neutron Diffusion theory and the Gamma transport calculation was performed with SN-Code(P
S
).
Asakura, Nobuyuki; Hoshino, Kazuo; Uto, Hiroyasu; Someya, Yoji; Tokunaga, Shinsuke; Shimizu, Katsuhiro; Suzuki, Satoshi; Tobita, Kenji; Ono, Noriyasu*; Ueda, Yoshio*; et al.
no journal, ,
Radiative cooling scenario by impurity seeding has been developed and the divertor geometry, and the plasma operation have been investigated for Demo with the fusion power of 1.5 GW, using SONIC simulation. Results showed the total peak heat load is reduced to less than 10 MWm
for the total radiation power fraction of 0.7-0.8. The heat load can be handled by the water-cooling and tungsten (W) monoblock target design, provided that Cu-alloy cooling pipe is applied. The design is applied only in the divertor target. F82H cooling pipe design will be applied for the divertor baffle and dome under higher neutron flux and lower heat load condition. Heat transport analysis of the target design and cooling-water pipes showed that the divertor design can handle the heat load distribution. The conceptual design study of the Demo divertor and power exhaust is presented. Development issues of physics, engineering and plasma material interaction from ITER technology will be also discussed.
