Development of plant lifecycle optimization method, ARKADIA for advanced reactors

Uchibori, Akihiro; Sogabe, Joji; Okano, Yasushi; Takata, Takashi*; Doda, Norihiro; Tanaka, Masaaki; Enuma, Yasuhiro; Wakai, Takashi; Asayama, Tai; Ohshima, Hiroyuki

Proceedings of Technical Meeting on State-of-the-art Thermal Hydraulics of Fast Reactors (Internet), 10 Pages, 2022/09

The ARKAIDA has been developed to realize automatic optimization of plant design from safety evaluation for the advanced reactors represented by a sodium-cooled fast reactor. ARKADIA-Design offers functions to support design optimization both in normal operating conditions and design basis events. The multi-level simulation approach by the coupled analysis such as neutronics, core deformation, core thermal hydraulics was developed as one of the main technologies of the ARKADIA-Design. On the other hand, ARKAIDA-Safety aims for safety evaluation considering severe accidents. As a key technology, the numerical methods for in- and ex-vessel coupled phenomena during severe accidents in sodium-cooled fast reactors were tested through a hypothetical severe accident event.

Discussion of uncertainties associated with parameters of biosphere model for safety assessment of geologieal disposal through sensitivity analysis

Kato, Tomoko; ; Suzuki, Yuji*;

JNC TN8400 2001-014, 212 Pages, 2001/03

JNC-TN8400-2001-014.pdf:19.25MB

Reference Biospheres are regarded as tools which can be used for making reasonable estimates of radiological impacts for the purposes of safety assessment of geological disposal. Moreover, those are available for reducing the uncertainties based on future human environments and lifestyles. On the other hand, it is recognised that the parameter values have some uncertainties derived from experimental or sampling errors. It is possible to estimate the impacts of these uncertainties throughout the model by sensitivity analysis. Thus for this study, to evaluate the impact of the variation of migration conditions and exposure pathways, we changed some of migration and exposure parameters in turn, which were used in the compartment model where the geosphere-biosphere interface is a river in a plain.

Basic data for integrated assessment of nuclear fuel cycle system

Nomura, Yasushi; Tamaki, Hitoshi; Ito, Chihiro*; Saegusa, Toshiari*

JAERI-Data/Code 2001-012, 118 Pages, 2001/03

JAERI-Data-Code-2001-012.pdf:5.71MB

no abstracts in English

ICONE-8 participation and investigation report of dry process in Argonne National Laboratory (ANL), USA

; Washiya, Tadahiro;

JNC TN8420 2001-009, 48 Pages, 2000/04

JNC-TN8420-2001-009.pdf:0.58MB

ICONE(International Conference on Nuclear Engineering) is an international conference on nuclear chemical engineering held among the United States, Japan and Europe, and ICONE8 (the 8th time of the conference) was held at Baltimore, USA on April 2 to 6, 2000. The authors of this paper reported the latest information on the reprocessing technology in the following session of the conference and audited the panel discussion and the technical report of the dry reprocessing technology etc. in the conference. (1)Investigation of Safety Evaluation Method and Application to Tokai Reprocessing Plant (TRP) in session of Track-5 "Non-reactor Safety and Reliability" (Nakamura) (2)Structural Improvement on the continuous rotary dissolver in session of Track-9 "Spent Nuclear Fuel and Waste Processing" (Washiya) (3)Development of Evaporators Made of Ti-5% Ta Alloy and Zr - Endurance Test By Mock-Up unit" in session of Track-2 "Aging and Modeling of Component Aging, Including corrosion of Metals and Welds.. passivation, and passive films" (Takata) At the conference, about 650 people participated from the United States, Japan, France, Canada and others, about700 research announcements, 7 keynote lecture and 8 panel discussion were done, flourishing with many participants. Moreover, as the conference was held in the year of 2000, the evaluation of this century and the direction of the next century of nuclear energy were discussed. After the conference, authors visited Argonne National Laboratory (ANL-E, ANL-W) and exchanged information concerning dry process with researchers of ANL-E and ANL-W, visiting ANL facilities. It was very significant to be able to acquire the information on the dry process developed in ANL and realize the device scale and the development environment, etc. and acquire technical information in detail which would not be able to obtain by engineering data, exchanging information with ANL engineers directly. It is suggested to be very valuable that the ...

Thermal hydraulic characteristics during ingress of coolant and loss of vacuum events in fusion reactors

Takase, Kazuyuki; Kunugi, Tomoaki*; Seki, Yasushi; Akimoto, Hajime

Nuclear Fusion, 40(3Y), p.527 - 535, 2000/03

https://doi.org/10.1088/0029-5515/40/3Y/313

no abstracts in English

None

Kagawa, Akio

JNC TN8200 2000-001, 40 Pages, 1999/10

JNC-TN8200-2000-001.pdf:0.79MB

None

Overall Safety Assessment of Geological Disposal and Apprecation of Probalistic Assessment

; ;

JAERI-M 87-040, 27 Pages, 1987/03

JAERI-M-87-040.pdf:0.9MB

no abstracts in English

Study on -Ray Irradiation Effects on Corrosion Resistance of Alloys for Storage of High-Level Waste Packages(I)

*; ; ; Araki, Kunio; *; *; *

JAERI-M 82-061, 28 Pages, 1982/07

JAERI-M-82-061.pdf:2.68MB

no abstracts in English

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.

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.