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Wada, Yuki; Shibamoto, Yasuteru; Hibiki, Takashi*
International Journal of Heat and Mass Transfer, 239, p.126598_1 - 126598_18, 2025/04
Times Cited Count：0 Percentile：0.00(Thermodynamics)Brear, D. J.*; Kondo, Satoru; Sogabe, Joji; Tobita, Yoshiharu*; Kamiyama, Kenji
JAEA-Research 2024-009, 134 Pages, 2024/10
JAEA-Research-2024-009.pdf:2.45MB
The SIMMER-III/SIMMER-IV computer codes are being used for liquid-metal fast reactor (LMFR) core disruptive accident (CDA) analysis. The sequence of events predicted in a CDA is often influenced by the heat exchanges between LMFR materials, which are controlled by heat transfer coefficients (HTCs) in the respective materials. The mass transfer processes of melting and freezing, and vaporization and condensation are also controlled by HTCs. The complexities in determining HTCs in a multi-component and multi-phase system are the number of HTCs to be defined at binary contact areas of a fluid with other fluids and structure surfaces, and the modes of heat transfer taking into account different flow topologies representing flow regimes with and without structure. As a result, dozens of HTCs are evaluated in each mesh cell for the heat and mass transfer calculations. This report describes the role of HTCs in SIMMER-III/SIMMER-IV, the heat transfer correlations implemented and the calculation of HTCs in all topologies in multi-component, multi-phase flows. A complete description of the physical basis of HTCs and available experimental correlations is contained in Appendices to this report. The major achievement of the code assessment program conducted in parallel with code development is summarized with respect to HTC modeling to demonstrate that the coding is reliable and that the model is applicable to various multi-phase problems with and without reactor materials.
Shimizu, Akira; Ohashi, Hirofumi; Kato, Michio; Hayashi, Koji; Aita, Hideki; Nishihara, Tetsuo; Inaba, Yoshitomo; Takada, Shoji; Morisaki, Norihiro; Sakaki, Akihiro*; et al.
JAERI-Tech 2005-031, 174 Pages, 2005/06
JAERI-Tech-2005-031.pdf:20.71MB
Connection of hydrogen production system by steam reforming of methane to the High Temperature Engineering Test Reactor (HTTR) of the Japan Atomic Energy Research Institute (JAERI) has been surveyed until now. Mock-up test facility of this steam reforming system with full-scale reaction tube was constructed in FY 2001, and a lot of operational test data on heat exchanges were obtained in these tests.In this report specifications, structures and heat transfer formulae of steam reformer, steam superheater, steam generator, condenser, helium gas cooler, feed gas heater and feed gas superheater were described. Evaluation codes were newly made to evaluate heat transfer characteristics from measured test data. Overall heat-transfer coefficient obtained from the experimental data were compared and evaluated with the prospective value calculated with heat transfer formulae. As a result, heat transfer performance and thermal efficiency of these heat exchangers were confirmed to be appropriate.
Horiguchi, Hironori; Oyama, Koji; Ishikuro, Yasuhiro; Hirane, Nobuhiko; Ito, Kazuhiro; Kameyama, Iwao
JAERI-Tech 2005-001, 38 Pages, 2005/02
JAERI-Tech-2005-001.pdf:2.79MB
After JRR-4 heat exchanger was renewed in made of stainless steel from carbon steel, it was examined how to manage the heat exchanger. The main subject is the cleaning technology of the heat exchanger. The recovery of old heat exchanger cooling performance has been by only chemical cleaning. Now we use chemical and dry cleaning as a new technique. It helps prevent of corrosions of secondary pipes and reduce of management costs. This report describes the performance management and cleaning technology of the JRR-4 heat exchanger and the management of the JRR-4 coolant.
Aso, Tomokazu; Sato, Hiroshi; Kaminaga, Masanori; Hino, Ryutaro; Monde, Masanori*
Proceedings of ICANS-XVI, Volume 2, p.935 - 944, 2003/07
no abstracts in English
Masaki, Kei; Taniguchi, Masaki; Miyo, Yasuhiko; Sakurai, Shinji; Sato, Kazuyoshi; Ezato, Koichiro; Tamai, Hiroshi; Sakasai, Akira; Matsukawa, Makoto; Ishida, Shinichi; et al.
Fusion Engineering and Design, 61-62, p.171 - 176, 2002/11
Times Cited Count：19 Percentile：74.08(Nuclear Science & Technology)A flat carbon fiber composite tile mock-up with screw tubes, which have helical fins like a nut, was fabricated aiming at further improvement of the heat removal performance of the cost-effectively manufactured divertor target for JT-60SC (modified JT-60 as a superconducting coil tokamak). The heat removal performance of the mock-up was successfully demonstrated on the JAERI Electron Beam Irradiation Stand. The estimated heat transfer coefficient of the screw tube at the non-boiling region was roughly 3 times higher than that of the smooth tube. This corresponds to 1.5 times that of the swirl tube. A heat cycle test of 10 MW/m2 showed that the mock-up with the screw tubes could withstand for 1400 cycles. These results indicate that the divertor target plate with the flat carbon fiber composite tile and the screw tube can be a promising candidate for the JT-60SC divertor target.
Kaminaga, Fumito*
JAERI-Tech 2002-012, 68 Pages, 2002/03
JAERI-Tech-2002-012.pdf:2.45MB
no abstracts in English
Iguchi, Tadashi
JAERI-Research 2000-050, 107 Pages, 2000/09
JAERI-Research-2000-050.pdf:4.29MB
no abstracts in English
Inagaki, Yoshiyuki
JAERI-Research 97-069, 31 Pages, 1997/10
JAERI-Research-97-069.pdf:1.02MB
no abstracts in English
Harayama, Yasuo; ; Aso, Tomokazu; Niimi, Motoji
JAERI-M 92-149, 78 Pages, 1992/10
no abstracts in English
Kato, Takashi; ; Hiyama, Tadao; Kawano, Katsumi; ; ; ; ; Tsuji, Hiroshi; ; et al.
Cryogenics, 32(92 SUPPL), p.260 - 263, 1992/00
no abstracts in English
Harayama, Yasuo; ; Hoshiya, Taiji
Journal of Nuclear Science and Technology, 28(10), p.961 - 964, 1991/10
no abstracts in English
Harayama, Yasuo; ; ; Nakamura, Jinichi; Uchida, Masaaki
JAERI-M 91-003, 38 Pages, 1991/02
no abstracts in English
Kumamaru, Hiroshige; ; Shimooke, Takanori; ; Kukita, Yutaka
Thermal Hydraulics of Advanced Heat Exchangers, p.31 - 37, 1991/00
no abstracts in English
G.Xu*; Kumamaru, Hiroshige; Tasaka, Kanji
JAERI-M 89-178, 35 Pages, 1989/11
no abstracts in English
; ; ; ; ;
Nucl.Eng.Des., 102, p.11 - 20, 1987/00
Times Cited Count：5 Percentile：50.37(Nuclear Science & Technology)no abstracts in English
; ; ; ; ;
Nucl.Eng.Des., 102, p.1 - 9, 1987/00
Times Cited Count：9 Percentile：66.31(Nuclear Science & Technology)no abstracts in English
Sudo, Yukio; Osakabe, Masahiro
Journal of Nuclear Science and Technology, 20(4), p.322 - 332, 1983/00
Times Cited Count：13 Percentile：78.50(Nuclear Science & Technology)no abstracts in English
; ; ; ; ;
JAERI-M 9910, 37 Pages, 1982/01
no abstracts in English
Sogabe, Joji; Kondo, Satoru*; Okano, Yasushi
no journal, ,
During severe accidents such as an anticipated transient without scram in sodium-cooled fast reactors, it is important to analyze multiphase multi-component flow behavior, when a part of disrupted core material is discharged outside the disrupted core region through control rod guide tubes (CRGTs). In particular, the fuel crust formation on a CRGT wall of the disrupted core side is an important phenomenon that affects the redistribution of disrupted fuel (the fuel discharged and the fuel remaining in the disrupted core region). Fast reactor safety analysis codes, SIMMER-III and SIMMER-IV, have been developed to evaluate the possibility of prompt criticality caused by the motion of molten core materials, and the material relocation of the disrupted core materials. This paper describes a developed model for phenomenological uncertainty of the fuel crust formation in core disruption phases in actual reactors. The model improves the applicability of the SIMMER code to the actual reactors.
