Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Nakatsuka, Toru; Tamai, Hidesada; Akimoto, Hajime
Proceedings of International Conference on Nuclear Energy System for Future Generation and Global Sustainability (GLOBAL 2005) (CD-ROM), 6 Pages, 2005/10
The subchannel analysis code NASCA was applied to critical power prediction of 37-rod tight-lattice bundle experiments which JAERI has been carrying out to confirm the thermal-hydraulic feasibility of the RMWR. The NASCA can yield good predictions of critical power for the gap width of 1.3 mm while the prediction accuracy of critical power deteriorated in case of the gap width of 1.0 mm. Predicted BT positions agree with the experimental results. Models in the code will be improved to consider the effect of the gap width based on further studies in the future.
Takase, Kazuyuki; Tamai, Hidesada; Yoshida, Hiroyuki; Akimoto, Hajime
Proceedings of International Meeting on Updates in Best EstimateMethods in Nuclear Installations Safety Analysis (BE-2004) (CD-ROM), p.151 - 152, 2004/11
no abstracts in English
Tada, Kenichi; Kondo, Ryoichi; Kamiya, Tomohiro; Nagatake, Taku; Ono, Ayako; Nagaya, Yasunobu; Yoshida, Hiroyuki
no journal, ,
JAEA has developed the multi-physics platform JAMPAN. In the previous presentation, we demonstrated a BWR single fuel assembly calculation by the coupling calculation of the continuous energy Monte Carlo calculation code MVP and the subchannel analysis code NASCA. The final goal of the MVP/NASCA coupling calculation is the whole core analysis. To achieve this, we implemented the flow rate calibration function in JAMPAN for the MVP/NASCA coupling calculation of the BWR multi-fuel assembly geometry.
Tada, Kenichi; Akie, Hiroshi; Kamiya, Tomohiro; Ono, Ayako; Nagaya, Yasunobu; Yoshida, Hiroyuki; Kawanishi, Tomohiro
no journal, ,
JAEA is developing the advanced neutronics/thermal-hydraulics coupling simulation system to improve the design and safety analysis of light water reactors. This presentation explains the coupling simulation system using a continuous energy Monte Carlo code MVP and a subchannel analysis code NASCA.
Tada, Kenichi; Kondo, Ryoichi; Kamiya, Tomohiro; Fukuda, Takanari; Ono, Ayako; Nagaya, Yasunobu; Yoshida, Hiroyuki
no journal, ,
JAEA has developed the multi-physics platform JAMPAN. In the previous presentation, we implemented the flow rate calibration function to JAMPAN for the MVP/NASCA coupling calculation of the BWR multi-fuel assembly geometry. Using this function, we performed the whole core coupling calculation using MVP/NASCA. For the whole BWR calculations, we prepared two types of input files. One is the hypothetical whole core geometry consisting of a 9
9 fuel assembly obtained from the OECD/NEA Phase-3C benchmark. The other is the initial loading core of Peach Bottom unit 2 obtained from the OECD/NEA Peach Bottom turbine trip benchmark. We will show the results of both whole-core BWR coupling calculations in the present presentation.
Tada, Kenichi; Akie, Hiroshi; Kamiya, Tomohiro; Nagaya, Yasunobu; Yoshida, Hiroyuki
no journal, ,
We implemented the handling module for the subchannel analysis code NASCA on the multi-physics platform JAMPAN. This function is used for the neutronics/thermal-hydraulics coupling simulation. The MVP/NASCA coupling calculation on JAMPAN will be applied to the large-scale calculation e.g., a whole core analysis. The calculation results of JAMPAN were compared to those of the prototype simulation system IPACS. The calculation results of JAMPAN showed good agreement with those of IPACS.
Tada, Kenichi
no journal, ,
JAEA has developed the multi-physics platform JAMPAN. In the previous presentation, we focused on the coupling of the neutronics and thermal-hydraulics calculations. In this presentation, we show the BWR single assembly coupling calculations results using the neutornics, thermal-hydraulics, and fuel performance calculations. FEMAXI-8 was used for the fuel performance calculation. FEMAXI-8 calculates the temperature distribution in the fuel rod including the fuel gap and surface heat flux for the neutronics and thermal-hydraulics calculations. We compare BWR single assembly coupling calculation results with and without FEMAXI-8. The BWR fuel assemblies from the OECD/NEA Peach Bottom turbine trip benchmark were used for these calculations.