PWR堆内构件可靠性

CRDM 棒控驱动机构 核电站 PWR

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Materials Reliability Program:

PWR Internals Material Aging

Degradation Mechanism Screening

and Threshold Values (MRP-175)

RIALNLICESED

MATE

CRDM 棒控驱动机构 核电站 PWR

CRDM 棒控驱动机构 核电站 PWR

Materials Reliability Program:

PWR Internals Material Aging

Degradation Mechanism Screening

and Threshold Values (MRP-175)

1012081

Topical Report, December 2005

EPRI Project Manager

H.T. Tang

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CRDM 棒控驱动机构 核电站 PWR

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CITATIONS

This report was prepared by

Framatome ANP, Inc.

3315 Old Forest Road

P.O. Box 10935

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Principal Investigator

S. Fyfitch

Contributors

H. Xu

K. Moore

R. Gurdal

This report describes research sponsored by the Electric Power Research Institute (EPRI).

The report is a corporate document that should be cited in the literature in the following manner:

Materials Reliability Program: PWR Internals Material Aging Degradation Mechanism

Screening and Threshold Values (MRP-175). EPRI, Palo Alto, CA: 2005. 1012081.

iii

CRDM 棒控驱动机构 核电站 PWR

CRDM 棒控驱动机构 核电站 PWR

REPORT SUMMARY

This report provides screening criteria and their technical bases for age-related degradation

evaluation of Pressurized Water Reactor (PWR) internals component items. It is a key element in

an overall strategy that uses knowledge of internals design, materials, and material properties and

applies screening methodologies for known age-related degradation mechanisms to manage the

effects of aging in PWR internals.

Background

The framework for implementation of an aging management program for PWR internals

components and using inspections and flaw tolerance evaluations to manage degradation issues

has been developed and is documented in MRP-134 and MRP-153. The important elements of

this framework are:

Screening, categorizing, and ranking PWR internals components for susceptibility and

significance to the age-related degradation mechanisms

Performing functionality analyses and safety assessment of PWR internals components to

define a safe and cost-effective aging management in-service inspection and evaluation

method and strategy

This report describes screening criteria and the associated technical bases for categorization and

ranking of aged PWR internals components.

Objectives

To establish technically sound age-related degradation mechanism screening criteria for

management of aging effects in PWR internals.

Approach

The principal investigators reviewed in detail the potential and observed age-related degradation

mechanisms and effects in PWR internals due to aging, such as irradiation-assisted stress

corrosion cracking (IASCC), irradiation embrittlement, void swelling, stress relaxation, and

fatigue. Based on available data and results, the investigators defined degradation threshold

values where possible and developed screening parameters and criteria …… 此处隐藏：13283字，全部文档内容请下载后查看。喜欢就下载吧 ……