SUBJECT: INEL NDE method applies to Fossil too!

A quick note to emphasize that the method described in the note I just sent you ALSO APPLIES TO NON-IRRADIATED COMPONENTS and therefore is a candidate for evaluating anything on a fossil plant. Many of you identified a major concern with high-energy steam piping….maybe we really have something here if it checks out.

SUBJECT: Possible breakthru — In-situ NDE of Nuclear components

(INEL HAS JUST PROVIDED THIS TO UFTO–LOOKS LIKE IT COULD BE VERY SIGNIFICANT. PLEASE REVIEW AND PASS ALONG TO APPROPRIATE PEOPLE IN YOUR COMPANY. FEEL FREE TO MAKE DIRECT CONTACT WITH THE INEL PEOPLE NAMED BELOW…LET ME KNOW IF ANYTHING COMES OF IT. THANKS, EDB)

“In Situ Nondestructive Examination Method for Characterization of Material Damage in Nuclear Power Plant Components”

Idaho National Engineering Laboratory November 1995

Capability and Relevance

The Idaho National Engineering Laboratory (INEL) is developing a unique application of a nondestructive examination method for aging assessment and life extension of nuclear power plant primary pressure boundary components.

A specific application is being developed for direct in situ measurements of fatigue damage in the components without knowing the prior operational history. The initial laboratory results show that this method can estimate fatigue damage ranging from a few percent to about 60 to 80 per cent of the fatigue life. We are now expanding the scope of this application to in situ estimate of radiation embrittlement damage in the pressure vessel steel materials (base metal, weld, heat affected zone) and of radiation damage in the stainless steel and Alloy 600 vessel internals.

What do we need from utilities?

We are seeking cooperative research and development agreements with nuclear power plant utilities for performing measurements to validate the capabilities and limitations of this application. The measurements would

also help to establish the correlations between the measurements and the mechanical properties of the irradiated pressure vessel materials.

Specific measurements to be performed include the following:

1. In situ measurements of fatigue damage in the light water reactor primary pressure boundary components, including primary coolant piping,

surge and spray line, other branch lines in PWR plants, and feedwater piping and nozzles in BWR plants.

2. In situ measurements of radiation embrittlement damage at the outside surface of reactor pressure vessel.

3. Measurements of radiation embrittlement damage in the surveillance capsules. These measurements will be correlated with the available measured data from the utility for reference nil-ductility transition temperature, Charpy upper shelf energy, and fracture toughness.

Contact Persons – Dr. V. N. Shah (Aging and Life Extension,

Lockheed Martin Idaho Technol Materials Characterization)

Idaho Falls, ID 83415-3870

Tel. No. (208)526-8639

Mr. D. W. Akers (NDE Method)

Lockheed Martin Idaho Technologies

Idaho Falls, ID 83415-2114

Tel. No. (208)526-6118