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Journal Articles

Subchannel analysis of 37-rod tight-lattice bundle experiments for reduced-moderation water reactor

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.

Journal Articles

Development of a best estimate analysis method on two-phase flow thermal-hydraulics for reduced-moderation water reactors

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

Oral presentation

Development of advanced neutronics/thermal-hydraulics coupling simulation system, 4; Neutronics/thermal-hydraulics coupling simulation using MVP and NASCA

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.

Oral presentation

Development of advanced neutronics/thermal-hydraulics coupling simulation system, 7; MVP/NASCA coupling calculation on JAMPAN

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.

Oral presentation

Development of advanced neutronics/thermal-hydraulics coupling simulation system, 10; Multi-assemblies coupling calculation using MVP/NASCA

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.

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