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Ono, Masahiro*; Uchibori, Akihiro; Okano, Yasushi; Takata, Takashi*
JAEA-Testing 2022-004, 193 Pages, 2023/03
JAEA-Testing-2022-004.pdf:3.31MB
A computer code TRACER (Transport phenomena of Radionuclides for Accident Consequence Evaluation of Reactor) version 2.4.1 has been developed to evaluate species and quantities of fission products (FPs) released into cover gas due to a fuel pin failure in an LMFBR. The TRACER version 2.4.1 includes the models related to NUREG-0772 and also new or modified computational program codes in order to possess a new function shown below, and partial modify of coefficient of FP transition model between coolant and cover gas. This manual includes manual conventions for TRACER Version 2.3, addition of reference such as formula, improvement of explanation of input file creation method, addition of improvement of NUREG-0772 model added to TRACER code, modification of figure of sample analysis performed in appendix. It includes modifications and additions of sample analysis.
Uchibori, Akihiro; Sonehara, Masateru; Aoyagi, Mitsuhiro; Takata, Takashi*; Ohshima, Hiroyuki
Proceedings of International Conference on Fast Reactors and Related Fuel Cycles; Sustainable Clean Energy for the Future (FR22) (Internet), 9 Pages, 2022/04
A new computational code, SPECTRA, has been developed for integrated analysis of in- and ex-vessel phenomena during severe accidents in sodium-cooled fast reactors. The in-vessel thermal hydraulics module includes coupled analytical models for multidimensional multifluid model considering compressibility and relocation of a molten core. A lumped mass model is employed for computing behavior of ex-vessel compressible multicomponent gas including aerosols. This model is coupled with the models for ex-vessel phenomena such as sodium fire. Loss of reactor level event starting from leakage of sodium coolant was computed. Basic capability to evaluate severe accident progress was demonstrated through this analysis.
Uchibori, Akihiro; Aoyagi, Mitsuhiro; Ito, Kei*; Takata, Takashi; Ohshima, Hiroyuki
no journal, ,
Development of the multi-scenario simulation systems for in-vessel/ex-vessel phenomena under severe accident in sodium cooled fast reactor is important issue. In this study, the basic modules for in-vessel/ex-vessel thermal hydraulics analysis were developed. The in-vessel basic module could evaluate phenomenon of coolant leakage in primary cooling system successfully. The ex-vessel basic module was validated through comparison to the analysis results by the other code or theoretical solutions.
Uchibori, Akihiro; Aoyagi, Mitsuhiro; Sonehara, Masateru; Takata, Takashi; Ohshima, Hiroyuki
no journal, ,
The multi-level, multi-scenario simulation systems have been developed as a fundamental technology of sodium-cooled fast reactors. In this study, a multi-scenario simulation system for in- and ex-vessel phenomena during a severe accident was newly developed. The validity of the system was confirmed through the analysis of a Loss-Of-Reactor-Level (LORL) event.