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Proceedings of 2003 International Congress on Advances in Nuclear Power Plants (ICAPP '03), P. 3330, 2003/00
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Yamadate, Megumi; Yamaguchi, Hiroyuki; Naganuma, Masayuki; Mizuno, Tomoyasu; Takaki, Naoyuki
JNC TN9400 2002-065, 131 Pages, 2002/12
JNC-TN9400-2002-065.pdf:8.23MB
Phase-II of the Feasibility Study on Commercialized Fast Reactor Cycle System in Japan (F/S) has been started since April 2001 and the design studies of various FR and recycle concepts are being conducted. In this report the JFY2001 studies of sodium cooled FR with mixed oxide fuel are summarized. The main results are as following. (1) Large scale reactors (1,500 MWe) (a) As for the large scale homogeneous ABLE type fuel core, we aimed to improve the effective average burn-up (that includes contribution of blankets) in order to reduce the fuel cycle cost. The specifications of Phase-I core and fuel were modified, which results in reducing the numbers of radial blanket sub-assemblies. As a result, the effective average burn-up was improved from 63 GWd/t to 77GWd/t. (b) As for the inner-duct sub-assembly core, the thickness of inner-duct was decided according to the evaluation of inner-duct expansion. As a result, the core reveals greater burn-up swing by about 0.6% 
k/kk' than that of the ABLE type fuel core. (c) As for the heterogeneous core, the inner-blanket shuffling concept was studied in order to improve the effective average burn-up and the thermal hydraulic characteristics, As a result, though the breeding ratio decreases in some extent, the possible improvement is obtained in the effective average burn-up (from 56 GWd/t to 80 GWd/t) and core thermal hydraulic design. (2) Medium scale reactors (500 MWe) (a) As for the medium scale core, with the aim of an attractive core concept the high internal conversion ration core was studied. As a result, the obtained typical core concept reveals around 1.05 of breeding ratio with core diameter 10% greater than conventional one and without radial blanket. The core achieves over 100 GWd/t of the effective average burn-up with the potential capability of long operation cycle.
Shimakawa, Yoshio; Ohshima, Hiroyuki; Okano, Yasushi; ; Kamiyama, Kenji; ;
JNC TN9400 2001-107, 147 Pages, 2001/11
JNC-TN9400-2001-107.pdf:5.26MB
The Phase I of feasibility study & commercialized fast reactor cycle systems was performed, and then a Large-scale (1500MWe) loop-type reactor (Twin plant type) and a medium-scale (500MWe) loop-type reactor (Modular type) have been screened as promising design concepts of sodium-cooled reactor. As a result of estimation for the economic competitiveness, prospect to attain the design goal (Plant construction const is below 200000yen/kWe) has been obtained for each concept, however, the cost of medium scale type reactor was higher than that of large scale type reactor, the necessity of further rationalization was indicated. In order to create and examine ideas for rationalization of medium-scale reactors, "Working group for creating new concepts of medium-scale reactors" was organized. In the group, not only a lot of ideas are proposed, classified and arranged but also seven important examination items are selected as subjects for commercialized FBR and concentrated arguments are held about them. This report summarizes the results of activity of this group.
; Sasaki, Makoto; *; *;
JNC TN9400 2001-113, 219 Pages, 2001/09
JNC-TN9400-2001-113.pdf:10.46MB
In the phase-I of the Feasibility Studies (F/S) on Commercialized Fast Reactor Cycle Systems from July 1999 to the end of FY2000, technology candidates of various commercialized fast reactor (FR) recycle concepts were investigated, in response to the JNC middle long term enterprise plan. This report describes about the core concept study of sodium-cooled oxide-fuel fast breeder reactors as a part of the investigation. The major results of JFY2000 are as follows: (1)One of the promising candidates of large and medium scale Na cooled oxide cores is radial heterogeneous core with axial blanket partial elimination driver fuel sub-assemblies, which achieves re-criticality free and high breeding capability. Core thermal hydraulic design is one of the technical matters of this concept to be investigated in detail. (2)There are concerns of core breeding capability of large scale Na cooled oxide core with the inner-duct sub-assembly concept. 0ne of the possible solutions of the concerns is selection radial heterogeneous core concept with inner-duct sub-assembly. (3)Results of core shielding analysis showed that feasible radial shielding thickness is 2 sub-assemblies layer for the core with radial blanket and 3 sub-assemblies layer for the core without radial blanket.
; Sasaki, Makoto; *; *;
JNC TN9400 2001-112, 174 Pages, 2001/09
JNC-TN9400-2001-112.pdf:8.09MB
As a part of phase-I of the Feasibility Studies of Commercialized Fast Reactor Cycle Systems (F/S), fast reactor core characteristics sensitivity study has been performed to understand the relationship between core performances of candidate concepts in the F/S and fuel specification variations, which correspond to the candidates of advanced fuel cycle technology concepts in the F/S, including fuel isotopic compositions. The major results of JFY2000 study are as follows: (1)It is indicated by neutronic calculation that change of core characteristic is not significant even the cases of variation of TRU composition and residual fission products in the recycled fuel which corresponds to advanced fuel cycle candidates. And such change is within a range in which significant modification of core design would not be required. (2)The core characteristic sensitivity study with oxide fuel concept options such as pellet, vi-pack, etc. indicated that the fuel smeared density variation has certain contribution to the core characteristic, especially to the breeding ration. The breeding ratio was calculated to be below l.2 even in the radial heterogeneous core if the fuel smeared density is as low as 80%TD. (3)Accessibility of irradiated radial blanket sub-assembly is evaluated in a viewpoint of proliferation resistance of core concept with radial blanket. The results showed that the heavy shielding and remote handling, similar to the general reprocessing plants, are indispensable to handle the irradiated radial blanket even after 5 years cooling.
Ota, Hirokazu*; Ogata, Takanari*; *; ; Hayashi, Hideyuki; ;
JNC TY9400 2001-015, 40 Pages, 2001/03
JNC-TY9400-2001-015.pdf:1.62MB
no abstracts in English
; Hayashi, Hideyuki; ; ; ; Takaki, Naoyuki;
JNC TY9400 2001-011, 493 Pages, 2001/03
JNC-TY9400-2001-011.pdf:20.55MB
no abstracts in English
