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Kikuchi, Norihiro; Imai, Yasutomo*; Yoshikawa, Ryuji; Doda, Norihiro; Tanaka, Masaaki
Proceedings of 28th International Conference on Nuclear Engineering (ICONE 28) (Internet), 8 Pages, 2021/08
In the design study of an advanced sodium-cooled fast reactor (Advanced-SFR) in JAEA, the use of a specific fuel assembly (FA) with an inner duct structure called FAIDUS has been investigated to enhance safety of Advanced-SFR. Due to the asymmetric layout of fuel rods by the inner duct, it is necessary to estimate the temperature distribution to confirm feasibility of FAIDUS. For the FAIDUS, confirmation of validity of the numerical results by a subchannel analysis code named ASFRE was not enough because the reference data on the thermal hydraulics in FAIDUS have not been obtained by the mock-up experiment, yet. Therefore, the code-to-code comparisons with numerical results of ASFRE and those of a CFD code named SPIRAL was conducted. The applicability of ASFRE was indicated through the confirmation of the consistency of mechanism of the specific temperature and velocity distributions appearing around the inner duct between the numerical results by ASFRE and those by SPIRAL.
*; Fusaeda, Shigeki*
JNC TJ1400 2000-004, 245 Pages, 2000/02
JNC-TJ1400-2000-004.pdf:8.57MB
no abstracts in English
*; Fusaeda, Shigeki*
JNC TJ1400 2000-003, 94 Pages, 2000/02
JNC-TJ1400-2000-003.pdf:4.63MB
no abstracts in English
*; *; Kugo, Teruhiko; Nakakawa, Masayuki; *; *
Nihon Genshiryoku Gakkai-Shi, 37(6), p.472 - 481, 1995/00
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)no abstracts in English
; ; ; Suzuki, Katsuo; *; *
JAERI-M 6945, 101 Pages, 1977/03
no abstracts in English
Kikuchi, Norihiro; Imai, Yasutomo*; Yoshikawa, Ryuji; Tanaka, Masaaki
no journal, ,
In design study of an advanced sodium-cooled fast reactor, adoption of Fuel Assembly (FA) with Inner DUct Structure (FAIDUS) has been investigated as one of the measures to enhance safety of the reactor. Numerical simulation of FAIDUS using subchannel analysis code named ASFRE for a design tool of FA was previously conducted to confirm its applicability to the thermal-hydraulics analysis in FAIDUS. In this study, numerical simulations of FAIDUS and a typical FA using detailed analysis code named SPIRAL under a high flow rate condition were performed. Numerical results using SPIRAL and ASFRE were well comparable. Applicability of ASFER for a thermal-hydraulic design tool of FAIDUS was potentially indicated in comparison with the results of SPIRAL.
Kikuchi, Norihiro
no journal, ,
In the design study of a sodium-cooled fast reactor (SFR) in JAEA, the adoption of a fuel assembly (FA) with an inner duct structure called FAIDUS has been investigated to enhance safety of SFR. Due to the asymmetric layout of fuel rods by addition of the inner duct, the velocity and temperature distributions in FAIDUS may differ from that in typical FA. It is need to confirmed that applicability of the subchannel analysis code named ASFRE which has been developed as a FA design tool, to thermal hydraulics analysis in FAIDUS. Because the reference data on the thermal hydraulics in FAIDUS have not been obtained by the mock-up experiment, the code-to-code comparisons with numerical results of ASFRE and those of a CFD code named SPIRAL was conducted. The applicability of ASFRE was indicated through the confirmation of the consistency of mechanism of the specific temperature and velocity distributions occurring around the inner duct between the numerical results by ASFRE and SPIRAL.
