Published July 19, 2012 | Version v1
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Design-reliability assurance program application to ACP600

  • 1. Technical Integration Division, CNNC China Nuclear Power Engineering Co., Ltd. No117, xisanhuanbeilu Haidian District Beijing 100840 (China)

Description

ACP600 is a newly nuclear power plant technology made by CNNC in China and it is based on the Generation III NPPs design experience and general safety goals. The ACP600 Design Reliability Assurance Program (D-RAP) is implemented as an integral part of the ACP600 design process. A RAP is a formal management system which assures the collection of important characteristic information about plant performance throughout each phase of its life and directs the use of this information in the implementation of analytical and management process which are specifically designed to meet two specific objects: confirm the plant goals and cost effective improvements. In general, typical reliability assurance program have 4 broad functional elements: 1) Goals and performance criteria; 2) Management system and implementing procedures; 3) Analytical tools and investigative methods; and 4) Information management. In this paper we will use the D-RAP technical and Risk-Informed requirements, and establish the RAM and PSA model to optimize the ACP600 design. Compared with previous design process, the D-RAP is more competent for the higher design targets and requirements, enjoying more creativity through an easier implementation of technical breakthroughs. By using D-RAP, the plants goals, system goals, performance criteria and safety criteria can be easier to realize, and the design can be optimized and more rational

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Part of:
Workshop on PSA for New and Advanced Reactors

Additional details

Publishing Information

Imprint Title
Workshop on PSA for New and Advanced Reactors
Imprint Pagination
733 p.
Journal Page Range
p. 338-353
Report number
NEA-CSNI-R--2012-2

Conference

Title
Workshop on PSA for New and Advanced Reactors
Dates
20-24 Jun 2011
Place
Paris (France)

INIS

Country of Publication
Nuclear Energy Agency of the OECD (NEA)
Country of Input or Organization
Nuclear Energy Agency of the OECD (NEA)
INIS RN
48018744
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
DESIGN; PROBABILISTIC ESTIMATION; PWR TYPE REACTORS; REACTOR SAFETY; RISK ASSESSMENT
Descriptors DEC
CALCULATION METHODS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
3 refs.