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Journal Articles

Development of structural design optimization process for an advanced sodium-cooled fast reactor

Kikuchi, Norihiro; Mori, Takero; Okajima, Satoshi; Tanaka, Masaaki; Miyazaki, Masashi

Proceedings of 30th International Conference on Nuclear Engineering (ICONE30) (Internet), 8 Pages, 2023/05

JAEA is developing an evaluation system aided by artificial intelligence (AI) named ARKADIA (Advanced Reactor Knowledge- and AI-aided Design Integration Approach through the whole plant lifecycle). A sub-system of it, named ARKADIA-Design, is being developed to support the design optimization study for an advanced nuclear plant including a sodium-cooled fast reactor (SFR). Authors are developing a design optimization process for the structure of the component in SFR. This paper describes the outline of a design optimization process, the brief introduction of evaluation methods for the process, and the result of the demonstration of the optimization process for a feasibility study. The development is being performed in a representative problem considering the thermal transient and seismic motion as a major issue in SFRs. Through the demonstration, it was confirmed that the optimization process under development may provide an optimal solution to the representative problem.

Journal Articles

Automatization of parametric analyses of influence factor on load derived from thermal transient in design optimization method for plant structure in sodium-cooled fast reactor

Kikuchi, Norihiro; Mori, Takero; Okajima, Satoshi; Tanaka, Masaaki; Miyazaki, Masashi

Dai-26-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu (Internet), 5 Pages, 2022/07

In JAEA, the design optimization method for plant structure has been developed on the process to output optimal solution of the thickness of reactor vessel wall against thermal transient and seismic loads in a SFR as a representative problem. Resistance characteristic of the wall on the load derived from thermal transient is one of the most important factors for safety estimation on the structural integrity. Failure probability of components against thermal transient was set to one of variables in the objective function for a common scale to compare with other variables in different failure mechanisms. In the iterative process to achieve the optimal solution, a number of evaluations to measure the influence on the load derived from thermal transient was necessarily conducted. More reduction of required time for evaluations is desired. To perform the iterative evaluation process efficiently, the automatization of parametric analyses was implemented in the optimization process.

JAEA Reports

Automation technique of analytical pre-treatment for radioactive sample measurement using the program written by visual basic for applications

Yamamoto, Masahiko; Karo, Yoshinori*; Kodaka, Noriyasu; Kuno, Takehiko

JAEA-Technology 2019-014, 68 Pages, 2019/10

JAEA-Technology-2019-014.pdf:2.93MB

Analytical devices like syringe pump, electric burette, fraction collector, and electric valve have been controlled by the program written with Visual Basic for Applications (VBA Macro) to automate the column separation of radioactive sample measurement. It is found that VBA Macro can control each device. Therefore, automatic conditioning and separation equipment were made by combining each device and sequentially controlling with the program. The automation conditioning equipment can repeatedly perform conditioning operation with maximum of 8 columns. The automation separation equipment can separate and recover Sr in simulated highly active liquid waste by using Eichrom Technologies Sr resin. It is found that the developed automation method, using commercially available VBA Macro, is effective to reduce labor work, operator's radiation exposure, and to prevent operational error of analysis, together with reducing the cost of automation.

Journal Articles

Performance test of automatic analysis system of strontium-90 in environmental sample

Fujita, Hiroki; Nojima, Takehiro; Nagaoka, Mika; Osawa, Takahito; Yokoyama, Hiroya; Ono, Hironobu*

KEK Proceedings 2016-8, p.168 - 172, 2016/10

An automatic analysis system was developed to analyze Strontium-90 ($$^{90}$$Sr) radioactivity in environmental sample for 2013-2015. Various kinds of ashed environmental samples were used in performance tests of the automatic system. These tests were successful without any system trouble. However, $$^{90}$$Sr concentration had not been measured using the samples analyzed by the system. In this research, $$^{90}$$Sr concentration in seaweed sample was compared by between the system's analysis and worker's one. Moreover, the system was improved in each analysis process.

Journal Articles

Development of automatic analysis system of Strontium-90 in environmental sample

Nojima, Takehiro; Fujita, Hiroki; Nagaoka, Mika; Osawa, Takahito; Yokoyama, Hiroya; Ono, Hironobu*

KEK Proceedings 2015-4, p.111 - 115, 2015/11

Automatic strontium-90 analysis system was developed for environmental sample in this research. The system was successful to do wet ashing, chemical separation and ion exchange processes using robot, automatic heating system and so on. Hand-made control program can operate the system by itself.

Journal Articles

Improvement of polarization measurement in JT-60 ECH system

Sato, Fumiaki*; Moriyama, Shinichi; Yokokura, Kenji; Shinozaki, Shinichi; Hiranai, Shinichi; Suzuki, Yasuo*; Seki, Masami

Heisei-14-Nendo Tokyo Daigaku Sogo Gijutsu Kenkyukai Gijutsu Hokokushu, 3 Pages, 2003/03

no abstracts in English

JAEA Reports

Desgin study of pyrochemical process operation by using virtual engineering models

Kakehi, Isao; Tozawa, Katsuhiro; ; ; *

JNC TN9400 2000-053, 99 Pages, 2000/04

JNC-TN9400-2000-053.pdf:7.47MB

This report describes accomplishment of simulations of Pyrochemical Process Operation by using virtual engineering models. The pyrochemical process using molten salt electrorefining would introduce new technologies for new fuels of particle oxide, particle nitride and metallic fuels. This system is a batch treatment system of reprocessing and re-fabrication, which transports products of solid form from a process to next process. As a result, this system needs automated transport system for process operations by robotics. ln this study, a simulation code system has been prepared, which provides virtual engineering environment to evaluate the pyrochemical process operation of a batch treatment system using handling robots. And the simulation study has been conducted to evaluate the required system functions, which are the function of handling robots, the interactions between robot and process equipment, and the time schedule of process, in the automated transport system by robotics. As a result of simulation of the process operation, which we have designed, the automated transport system by robotics of the pyrochemical process is realistic. And the issues for the system development have been pointed out.

Journal Articles

Risk management and human; Toward ecological interface beyond automatization and procedurization

Tanabe, Fumiya

SCIaS, 5(3), p.22 - 23, 2000/03

no abstracts in English

JAEA Reports

Development of JRR-4 operation support system

Takahashi, Hiroki; Yamamoto, Kazuyoshi; Yoritsune, Tsutomu; ;

JAERI-Tech 99-037, 44 Pages, 1999/03

JAERI-Tech-99-037.pdf:2.15MB

no abstracts in English

JAEA Reports

Development of advanced automatic operation system for nuclear ship, 1; Perfect automatic normal operation

Nakazawa, Toshio; Yabuuchi, Noriaki; Takahashi, Hiroki; Shimazaki, Junya

JAERI-Tech 99-008, 45 Pages, 1999/02

JAERI-Tech-99-008.pdf:1.84MB

no abstracts in English

JAEA Reports

The Development of Radiation Hardened Microcomputer System; System Design

Ishibashi, Yuzo; Kuroda, Yoshikatsu*; Nakajima, Atsushi*

PNC TJ8216 98-003, 243 Pages, 1998/03

PNC-TJ8216-98-003.pdf:6.5MB

no abstracts in English

Journal Articles

In order to realize a nuclear ship

Fune No Kagaku, 51(1), p.68 - 74, 1998/01

no abstracts in English

Journal Articles

Ultrasonic testing

Ooka, Norikazu;

Keikinzoku Yosetsu, 36(5), p.216 - 221, 1998/00

no abstracts in English

JAEA Reports

Development of advanced automatic control system for nuclear ship, 2; Perfect automatic operation after reactor scram events

Yabuuchi, Noriaki; Nakazawa, Toshio; Takahashi, Hiroki; Shimazaki, Junya; Hoshi, Tsutao

JAERI-Tech 97-057, 54 Pages, 1997/11

JAERI-Tech-97-057.pdf:2.03MB

no abstracts in English

JAEA Reports

None

Kato, Masato; ; ;

PNC TN8410 97-065, 147 Pages, 1997/03

PNC-TN8410-97-065.pdf:64.31MB

None

JAEA Reports

None

*

PNC TJ8005 97-001, 122 Pages, 1997/03

PNC-TJ8005-97-001.pdf:27.46MB

no abstracts in English

JAEA Reports

None

*

PNC TJ7694 96-001, 171 Pages, 1996/02

PNC-TJ7694-96-001.pdf:6.53MB

no abstracts in English

Journal Articles

Integral-type small reactor MRX and its applications

Shimazaki, Junya; Ochiai, Masaaki; Ishida, Toshihisa; Hoshi, Tsutao

10th Pacific Basin Nuclear Conf. (10-PBNC), p.828 - 833, 1996/00

no abstracts in English

JAEA Reports

None

; ; ;

PNC TN8420 93-011, 40 Pages, 1993/07

PNC-TN8420-93-011.pdf:2.39MB

None

JAEA Reports

None

; ; Komatsuzaki, Kenji;

PNC TN8520 93-002, 191 Pages, 1993/03

PNC-TN8520-93-002.pdf:4.47MB

None

34 (Records 1-20 displayed on this page)