Published 2005 | Version v1
Book

Study of visualized analysis platform for nuclear fuel cycle system based on multilevel flow model

Creators

  • 1. Graduate School of Energy Science, Kyoto University (Japan)

Description

Complex Nuclear Fuel Cycle (NFC) system faces many socio-technical issues that need to obtain the consensus between stake holders of different knowledge background. In this paper, a visualized analysis platform based on graphical functional modeling method, Multilevel Flow Model (MFM), was proposed to help those stake holders to recognize and analyze various socio-technical issues in NFC system. There are some new functions, such as 'Reaction Function', 'Switch Function' and 'Conversion Function', introduced to adapt new simulation tasks for NFC system. Based upon this methodology, a micro-process and a macro-process of NFC system were simulated and meanwhile some key analysis variables required by some analysis methods were deducted and displayed in the platform. And finally a simple simulation analysis was conducted based on the proposed MFM application. (author)

Part of:
The 13th international conference on nuclear engineering abstracts

Additional details

Publishing Information

Publisher
Atomic Energy Press
Imprint Place
Beijing (China)
ISBN
7-5022-3400-4
Imprint Title
The 13th international conference on nuclear engineering abstracts
Imprint Pagination
604 p.
Journal Page Range
p. 303-304

Conference

Title
13. international conference on nuclear engineering
Dates
16-20 May 2005
Place
Beijing (China)

INIS

Country of Publication
China
Country of Input or Organization
China
INIS RN
38036586
Subject category
S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CONVERSION; ENVIRONMENTAL IMPACTS; EVALUATION; FLOW MODELS; FUEL CYCLE; FUNCTIONS; HAZARDS; NUCLEAR FUELS; NUCLEAR POWER; RADIOACTIVE MATERIALS; SIMULATION; SWITCHES; URANIUM; USES
Descriptors DEC
ACTINIDES; ELECTRICAL EQUIPMENT; ELEMENTS; ENERGY SOURCES; EQUIPMENT; FUELS; MATERIALS; MATHEMATICAL MODELS; METALS; POWER; REACTOR MATERIALS

Optional Information