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JAEA Reports

Development of an on-site plant analyzer (1); Development of a GUI for building plant models for analyzes and retrieval of real-time plant data

JNC TN4400 2000-002, 33 Pages, 2000/06

JNC-TN4400-2000-002.pdf:5.22MB

An on-site plant analyzer can provide analysis support in evaluating plant dynamic characteristics when unplanned events occur in a nuclear power station. The plant analyzer contains a plant-dynamics analysis code, which efficiently and quickly analyzes the plant dynamic characteristics. Elements being developed for the on-site plant analyzer include utilities to build plant models for performing analyses and to retrieve plant operation data. The addition of these elements to the analysis code supports the plant-dynamics analysis works in MONJU, in particular, to assist the analyses of start up tests. The system contains the FBR plant-dynamics analysis code "Super-COPD", which is based on the "COPD" code that was used in the safety licensing of MONJU. One feature of the system is that all operations, e.g., assembling plant models for analysis, are prepared using a GUI (Graphical user Interface). In addition to this feature, the system is able to retrieve directly on- and off-line plant data from MIDAS, the Monju Integrated Data Acquisition System. These plant data are used to supply time-dependent boundary conditions for the plant analysis models. For this report, two case studies were performed. First, the analysis result of a turbine trip test at 40% power operation using the full plant model is described. For the second, performance of the IHX model was evaluated using retrieved plant data for boundary conditions. With the development of this system, improvement in the efficiency of analyses of MONJU start-up tests is expected.

JAEA Reports

None

Noda, Masaru*

JNC TJ1400 99-035, 256 Pages, 1999/02

JNC-TJ1400-99-035.pdf:21.56MB

no abstracts in English

Journal Articles

Tritium behavior in fusion reactor facilities and the environment, 3; Tritium behavior in fusion fuel systems

Yamanishi, Toshihiko; Nishikawa, Masabumi*; *

Purazuma, Kaku Yugo Gakkai-Shi, 73(12), p.1326 - 1332, 1997/12

no abstracts in English

JAEA Reports

Accident identification in tritium processing systems of international thermonuclear experimental reactor in engineering design activity

Enoeda, Mikio; D.F.Holland*; Matsuda, Yuji; Ohira, Shigeru; Okuno, Kenji; *; Hirata, Shingo*

JAERI-Tech 95-050, 90 Pages, 1995/11

JAERI-Tech-95-050.pdf:2.98MB

no abstracts in English

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