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Technical feasibility and reliability of passive safety systems of AC600

Abstract

The first step conceptual design of the 600 MWe advanced PWR (AC-600) has been finished. Experiments on the passive system of AC-600 are being carried out, and are expected to be completed next year. The main research emphases of AC-600 conceptual design include the advanced core, the passive safety system and simplification. The design objective of AC-600 is that the safety, reliability, maintainability, operation cost and construction period are all improved upon compared to those of PWR plant. One of important means to achieve the objective is using a passive system, which has the following functions whenever its operation is required: providing the reactor core with enough coolant when others fail to make up the lost coolant; reactor residual heat removal; cooling and reducing pressure in the containment and preventing radioactive substances from being released into the environment after occurrence of accident (e.g. LOCA). The system should meet the single failure criterion, and keep operating when a single active component or passive component breaks down during the first 72 hour period after occurrence of accident, or in the long period following the 72 hour period. The passive safety system of AC-600 is composed of the primary safety injection system, the  More>>
Authors:
Niu, W; Zeng, X [1] 
  1. Nuclear Power Inst. of China, Chendu (China)
Publication Date:
Dec 01, 1996
Product Type:
Conference
Report Number:
IAEA-TECDOC-920; CONF-9411339-
Reference Number:
SCA: 210200; PA: AIX-28:021791; EDB-97:039722; SN: 97001747502
Resource Relation:
Conference: Advisory group meeting on technical feasibility and reliability of passive safety systems for nuclear power plants, Juelich (Germany), 21-24 Nov 1994; Other Information: PBD: Dec 1996; Related Information: Is Part Of Technical feasibility and reliability of passive safety systems for nuclear power plants. Proceedings of an advisory group meeting; PB: 357 p.
Subject:
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; PWR TYPE REACTORS; REACTOR SAFETY; DESIGN; FEASIBILITY STUDIES; MODIFICATIONS; REACTOR SAFETY EXPERIMENTS; RELIABILITY; SAFETY ENGINEERING
OSTI ID:
443191
Research Organizations:
International Atomic Energy Agency, Vienna (Austria)
Country of Origin:
IAEA
Language:
English
Other Identifying Numbers:
Journal ID: ISSN 1011-4289; Other: ON: DE97615987; TRN: XA9743168021791
Availability:
INIS; OSTI as DE97615987
Submitting Site:
INIS
Size:
pp. 183-191
Announcement Date:
Mar 20, 1997

Citation Formats

Niu, W, and Zeng, X. Technical feasibility and reliability of passive safety systems of AC600. IAEA: N. p., 1996. Web.
Niu, W, & Zeng, X. Technical feasibility and reliability of passive safety systems of AC600. IAEA.
Niu, W, and Zeng, X. 1996. "Technical feasibility and reliability of passive safety systems of AC600." IAEA.
@misc{etde_443191,
title = {Technical feasibility and reliability of passive safety systems of AC600}
author = {Niu, W, and Zeng, X}
abstractNote = {The first step conceptual design of the 600 MWe advanced PWR (AC-600) has been finished. Experiments on the passive system of AC-600 are being carried out, and are expected to be completed next year. The main research emphases of AC-600 conceptual design include the advanced core, the passive safety system and simplification. The design objective of AC-600 is that the safety, reliability, maintainability, operation cost and construction period are all improved upon compared to those of PWR plant. One of important means to achieve the objective is using a passive system, which has the following functions whenever its operation is required: providing the reactor core with enough coolant when others fail to make up the lost coolant; reactor residual heat removal; cooling and reducing pressure in the containment and preventing radioactive substances from being released into the environment after occurrence of accident (e.g. LOCA). The system should meet the single failure criterion, and keep operating when a single active component or passive component breaks down during the first 72 hour period after occurrence of accident, or in the long period following the 72 hour period. The passive safety system of AC-600 is composed of the primary safety injection system, the secondary emergency core residual heat removal system and the containment cooling system. The design of the system follows some relevant rules and criteria used by current PWR plant. The system has the ability to bear single failure, two complete separate subsystems are considered, each designed for 100% working capacity. Normal operation is separate from safety operation and avoids cross coupling and interference between systems, improves the reliability of components, and makes it easy to maintain, inspect and test the system. The paper discusses the technical feasibility and reliability of the passive safety system of AC-600, and some issues and test plans are also involved. (author). 3 figs, 1 tab.}
place = {IAEA}
year = {1996}
month = {Dec}
}