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Kamiya, Tomohiro; Nagatake, Taku; Ono, Ayako; Tada, Kenichi; Kondo, Ryoichi; Nagaya, Yasunobu; Yoshida, Hiroyuki
Mechanical Engineering Journal (Internet), 12(4), p.24-00461_1 - 24-00461_9, 2025/08
JAEA has developed the JAEA Advanced Multi-Physics Analysis platform for Nuclear systems (JAMPAN) to realize high-fidelity neutronics/thermal-hydraulics coupling simulations. We performed a neutronics/thermal-hydraulics coupling simulation for a single BWR fuel assembly in order to confirm that the MVP/JUPITER coupling through JAMPAN is feasible. As a result, we confirmed that the void fraction and the corresponding change in the heat generation distribution are reasonable qualitatively.
Kamiya, Tomohiro; Nagatake, Taku; Ono, Ayako; Tada, Kenichi; Kondo, Ryoichi; Nagaya, Yasunobu; Yoshida, Hiroyuki
Proceedings of 31st International Conference on Nuclear Engineering (ICONE31) (Internet), 7 Pages, 2024/11
We have developed the JAEA Advances Multi-Physics Analysis platform for Nuclear systems (JAMPAN) to realize high-fidelity neutronics/thermal-hydraulics coupling simulations. We will perform MVP/JUPITER coupling simulation for a single BWR fuel assembly in order to confirm that the neutronics/thermal-hydraulics coupling through JAMPAN is feasible. This presentation explains how to send and receive data between MVP and JUPITER through JAMPAN and simulation results.
Tada, Kenichi
Robutsuri No Kenkyu (Internet), (77), 6 Pages, 2024/06
The author participated in the international conference on reactor physics (Physor2024) held in San Francisco, U.S.A. from April 21 to 24, 2024. This article shows the overview of two workshops, i.e., the demonstration of the multi-physics platform Kraken at VTT and MOOSE at INL, the overview of two sections, i.e., "Data Methods, Code Validation" and "Multi-Physics Reactor Simulations and Validation", and the author's impressions of the conference.
Tada, Kenichi; Kondo, Ryoichi; Kamiya, Tomohiro; Nagatake, Taku; Ono, Ayako; Nagaya, Yasunobu; Yoshida, Hiroyuki
Proceedings of International Conference on Physics of Reactors (PHYSOR 2024) (Internet), p.1488 - 1497, 2024/04
JAEA has developed a new high-fidelity multi-physics platform JAMPAN for connecting single-physics codes such as a neutronics code and a thermal-hydraulics code. It consists of the HDF5 formatted data container and input and output data handler modules to generate the input file and read the output file of the single-physics code. Users can easily add or exchange the code by implementing input and output data handler modules for this code. The first target of JAMPAN is the coupling of neutronics and thermal-hydraulics calculations to provide reference results of core analysis codes. The current version of JAMPAN couples the neutronics code MVP and the thermal-hydraulics codes JUPITER, ACE-3D, and NASCA. Users can select the thermal-hydraulics code depending on the scale of problems to be solved, computational performance, and so on. This presentation explains the overview of JAMPAN and shows the results of the neutronics and thermal-hydraulics coupling calculation.
Yoshida, Hiroyuki
no journal, ,
no abstracts in English
Tada, Kenichi
no journal, ,
JAEA has developed a Python-based multi-physics platform JAMPAN. We have realized a single BWR assembly geometry calculation using MVP/JUPITER and whole BWR core calculations using MVP/NASCA in this fiscal year. 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 are coupling the light water fuel performance analysis code FEMAXI-8. The first target of the coupling of FEMAXI-8 is the calculation of temperature distribution and heat conduction in the fuel rod such as the gap conductance. The coupling of the other calculation functions will be considered in the future.
Fukuda, Takanari; Yoshida, Hiroyuki; Kamiya, Tomohiro; Suzuki, Takayuki*; Tada, Kenichi; Nagaya, Yasunobu
no journal, ,
JAEA has been engaged in the development of JAMPAN, a platform for multi-physics simulations, to enable the numerical simualtons for enhancing the quality and safety of the light water reactor design. In this study, ACE-3D, which is based on a three-dimensional two-fluid model capable of general-purpose multidimensional thermal-hydraulic calculations, was selected as the thermal-hydraulic calculation code. Furthermore, a JAMPAN module was developed to facilitate a coupled MVP/ACE-3D neutronics/thermal-hydraulics simulation. In the presentation, the results of the simulation for an 88 BWR fuel assembly with JAMPAN will be presented.
Yoshida, Hiroyuki; Kamiya, Tomohiro; Tada, Kenichi
no journal, ,
no abstracts in English
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.
Tada, Kenichi; Kondo, Ryoichi; Kamiya, Tomohiro; Nagatake, Taku; Ono, Ayako; Nagaya, Yasunobu; Yoshida, Hiroyuki
no journal, ,
JAEA has developed a Python-based multi-physics platform JAMPAN. This platform has an HDF5 formatted JAMPAN data container. It connects calculation codes via this data container. The utilization of this container eliminates the dependence on the calculation code and enables us to easily exchange the coupling code. The first target of JAMPAN is a coupling of neutronics and thermal hydraulics codes to provide reference results of core analysis codes. The coupling of the other codes such as a fuel performance analysis code FEMAXI is future work. This presentation shows the overview of the JAMPAN platform.
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.
Kamiya, Tomohiro; Nagatake, Taku; Ono, Ayako; Tada, Kenichi; Kondo, Ryoichi; Nagaya, Yasunobu; Yoshida, Hiroyuki
no journal, ,
JAEA has developed a platform JAMPAN for multi-physics simulations, has improved a neutronics analysis code, and has improved and validated thermal-hydraulics analysis codes to improve the design and the safety of light water reactors. The objective is implementing the coupling modules between the neutronics code MVP and the thermal-hydraulics code JUPITER, and verifying the modules. A fuel bundle geometry under a normal operation condition of a BWR was used for the neutronics and thermal-hydraulics coupling simulation to verify the modules. In this presentation, we will explain how to send and receive data between MVP and JUPITER through JAMPAN and show the results of the neutronics/thermal-hydraulics coupling simulations using MVP and JUPITER.
Tada, Kenichi
no journal, ,
JAMPAN is a new high-fidelity multi-physics simulation platform for connecting single-physics codes such as a neutronics calculation code and a thermal-hydraulics calculation code. JAMPAN has an HDF5 formatted date container to handle input and output data of each single-physics code. This JAMPAN data container is designed to be independent of single-physics codes. This data container allows users to easily add or replace calculation codes without considering the data format of other physics codes. The first target of JAMPAN is the coupling of neutronics and thermal hydraulics calculations for BWR and PWR. The current version of JAMPAN treats MVP for the neutronics calculation and JUPITER, ACE-3D, and NASCA for the thermal-hydraulics calculation. Users can select the thermal-hydraulics code according to the computational geometry. JUPITER is used for the single assembly geometry. ACE-3D and NASCA are used for the whole core geometry. This presentation explains the overview of JAMPAN.
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 99 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.
Kamiya, Tomohiro
no journal, ,
We have developed the JAEA Advances Multi-Physics Analysis platform for Nuclear systems (JAMPAN) to realize high-fidelity neutronics/thermal-hydraulics coupling simulations. We performed MVP/JUPITER coupling simulation for a single BWR fuel assembly in order to confirm that the neutronics/thermal-hydraulics coupling through JAMPAN is feasible. This presentation explains how to send and receive data between MVP and JUPITER through JAMPAN and simulation results.
Tada, Kenichi
no journal, ,
This presentation explains the overview and current status of the JAEA Advanced Multi-Physics Analysis platform for Nuclear Systems JAMPAN. Validation of nuclear reactor design codes requires comparison with experimental data. Though multi-physics experimental data are desired for it, it is difficult to measure such data for a wide range of operation conditions. The preparation of the high-fidelity multi-physics simulation results which are substitutes for experimental data is required to reduce the number of experimental data. JAEA started to develop the multi-physics platform JAMPAN in 2021 to provide high-reliability multi-physics calculation results.
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, ,
This presentation explains the handling of the GNDS format in the nuclear data processing code FRENDY. The purpose of this meeting is not only the handling of the GNDS format but also the high-fidelity multi-physics simulation efforts. We also present the overview of the high-fidelity multi-physics simulation platform JAMPAN.
