Refine your search:     
Report No.
 - 
Search Results: Records 1-6 displayed on this page of 6
  • 1

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Oral presentation

Development of multi-level, multi-scenario simulation systems for sodium cooled fast reactor, 6; Development of basic module in multi-scenario simulation system

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.

Oral presentation

Development of multi-level, multi-scenario simulation systems for sodium cooled fast reactor, 16; Development of integrated analysis system for in- and ex-vessel phenomena

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.

Oral presentation

Development of advanced reactor knowledge- and AI-aided design integration approach through the whole plant lifecycle, ARKADIA, 3; Development plan of safety evaluation tool, ARKADIA-Safety

Uchibori, Akihiro; Takata, Takashi; Fukano, Yoshitaka; Yamano, Hidemasa

no journal, , 

The development of ARKADIA-Safety for safety evaluation and design optimization considering severe accident was started. This development includes improvement and applicability expansion of the in- and ex-vessel analysis code, SPECTRA. Furthermore, optimization of the containment vessel considering severe accident will be performed as an example application of ARKADIA-Safety.

Oral presentation

Development of fission product chemistry database ECUME for improved source term estimation method, 1; Dataset for chemical reaction kinetics

Miwa, Shuhei; Horiguchi, Naoki; Miyahara, Naoya*; Nakajima, Kunihisa; Suzuki, Eriko; Imoto, Jumpei; Liu, J.; Karasawa, Hidetoshi; Osaka, Masahiko

no journal, , 

We developed the fission product chemistry database named ECUME ($$underline{E}$$ffective $$underline{C}$$hemistry database of fission products $$underline{U}$$nder $$underline{M}$$ultiphase r$$underline{E}$$action) for the LWR severe accident. The dataset for chemical reaction kinetics of ECUME consists of main chemical reactions and their effective chemical reaction kinetic constants. This dataset has the advantages in kinetics evaluation of the effects of molybdenum and BWR control material boron on cesium and iodine chemistry. This can improve prediction accuracy of chemical forms and their fraction in lower temperature region such as a primary containment vessel and a reactor building.

Oral presentation

Development of fission product chemistry database ECUME for improved source term estimation method, 2; Elemental model set

Suzuki, Eriko; Nakajima, Kunihisa; Nishioka, Shunichiro*; Miwa, Shuhei; Horiguchi, Naoki; Imoto, Jumpei; Liu, J.; Karasawa, Hidetoshi; Osaka, Masahiko

no journal, , 

The elemental model set (EM) of ECUME consists of improved models which can be directly incorporated into the present severe accident analysis codes. The models of EM has advantages in considering various chemical conditions. The improved model for cesium (Cs) chemisorption has successfully reproduced the effects of Cs vapor concentration in gas phase and silicon content in stainless steel on the Cs chemisorption behavior. This improved model can contribute to more accurate estimation of Cs distribution in a high temperature area.

Oral presentation

Development of advanced reactor knowledge- and AI-aided design integration approach through the whole plant lifecycle, ARKADIA, 6; Development of ex-vessel analysis model in ARKADIA-Safety for safety evaluation

Uchibori, Akihiro; Aoyagi, Mitsuhiro; Sonehara, Masateru; Sogabe, Joji; Okano, Yasushi; Takata, Takashi*

no journal, , 

The ARKADIA-Safety for safety evaluation and design optimization considering severe accident has been developed. This paper presents validation of sodium fire analysis model and integration of ex-vessel analysis model for improvement of the evaluation method.

6 (Records 1-6 displayed on this page)
  • 1