Published October 2012 | Version v1
Book Metadata-only

Analysis of appraisal tool of system security engineering capability maturity based on component

Creators

  • 1. Nuclear Energy Economics and Management Research Center University of South China, Hengyang (China)
  • 2. School of Computer and Technology University of South China, Hengyang (China)

Description

Spent Fuel Reprocessing is a part of nuclear fuel cycle and is the inevitably choice of nuclear power sustainable development. Reprocessing needs to face with radiological, criticality, chemical hazards. Besides using the tradition appraisal methods based on the security goals, it is a beneficial supplement that using the appraisal method of system security engineering capability maturity model based on the process. Experts should check and approve large numbers of documents during the appraisal based on system security engineering capability maturity model, so it is necessary that developing a tool to assist the expert to complete the appraisal. The method of developing software based on component is highly effective, nimble and reliable. Component technology is analyzed, the methods of extraction model domain components and general components is introduced, and the appraisal system is developed based on component technology. (authors)

Part of:
Progress report on nuclear science and technology in China (Vol.2). Proceedings of academic annual meeting of China Nuclear Society in 2011, No.10--nuclear Information sub-volume

Additional details

Publishing Information

Publisher
Atomic Energy Press
Imprint Place
Beijing (China)
ISBN
978-7-5022-5609-8
Imprint Title
Progress report on nuclear science and technology in China (Vol.2). Proceedings of academic annual meeting of China Nuclear Society in 2011, No.10--nuclear Information sub-volume
Imprint Pagination
153 p.
Journal Page Range
p. 111-116

Conference

Title
2011 academic annual meeting of China Nuclear Society
Dates
11-14 Oct 2011
Place
Beijing (China)

INIS

Country of Publication
China
Country of Input or Organization
China
INIS RN
46041207
Subject category
S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S97: MATHEMATICAL METHODS AND COMPUTING;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPUTER CODES; COST ESTIMATION; CRITICALITY; EFFICIENCY; ENGINEERING; EVALUATION; FUEL CYCLE; HAZARDS; MATHEMATICAL MODELS; NUCLEAR POWER; RELIABILITY; REPROCESSING; RISK ASSESSMENT; SAFETY; SPENT FUELS; SUSTAINABLE DEVELOPMENT
Descriptors DEC
ENERGY SOURCES; FUELS; MATERIALS; NUCLEAR FUELS; POWER; REACTOR MATERIALS; RESOURCE DEVELOPMENT; SEPARATION PROCESSES

Optional Information

Notes
5 figs., 1 tabs., 9 refs.