Sensor for monitoring corrosion on a member in a nuclear reactor

Induced nuclear reactions: processes – systems – and elements – Testing – sensing – measuring – or detecting a fission reactor...

Patent

Rate now

  [ 0.00 ] – not rated yet Voters 0   Comments 0

Details

376305, 324700, G21C 1700

Patent

active

051223309

ABSTRACT:
An apparatus and method for monitoring corrosion to members within the core of a nuclear reactor, particularly fuel rod cladding. A sensor means is submerged inside the core of a nuclear reactor near the member of fuel rods. The sensor means is comprised of a generally cylindrical section having an outer surface that is subject to corrosion and radiation, and has a cross-sectional area A.sub.1. The sensor means additionally has a reference section subjected to radiation but not to corrosion, and having a cross-sectional area A.sub.2. At least one pair of first probes, separated by a length L.sub.1, is placed in electrical contact with the cylindrical section. At least one pair of second probes separated by a length L.sub.2, is placed in electrical contact with the reference section. A current is passed throughout the sensor means to produce a potential gradient in the cylindrical section and reference section. The change in potential in the reference section, and the cylindrical section is measured and used to calculate the subsequent cross-sectional area in the cylindrical section between the first probes. Preferably, the cylindrical section and reference section are made from the same material as the member.

REFERENCES:
patent: 3042863 (1962-07-01), Marsh et al.
patent: 3197724 (1965-07-01), Marsh
patent: 3358229 (1967-12-01), Collins
patent: 3599090 (1971-08-01), Fitzpatrick et al.
patent: 3604102 (1971-09-01), Boccalari et al.
patent: 3854087 (1974-12-01), Frenck et al.
patent: 3913208 (1975-10-01), Colombi et al.
patent: 4338563 (1982-07-01), Rhoades et al.
patent: 4677855 (1987-07-01), Coffin, Jr. et al.
patent: 4924708 (1990-05-01), Solomon et al.
Urquhart, A. W. and D. A. Vermilyea, "A Preliminary Correlation Between the Accelerated Corrosion of Zircaloy in BWR's and in High Temperature, High Pressure Steam" Journal of Nuclear Materials, Jun., 1976, pp. 111-114.

LandOfFree

Say what you really think

Search LandOfFree.com for the USA inventors and patents. Rate them and share your experience with other people.

Rating

Sensor for monitoring corrosion on a member in a nuclear reactor does not yet have a rating. At this time, there are no reviews or comments for this patent.

If you have personal experience with Sensor for monitoring corrosion on a member in a nuclear reactor, we encourage you to share that experience with our LandOfFree.com community. Your opinion is very important and Sensor for monitoring corrosion on a member in a nuclear reactor will most certainly appreciate the feedback.

Rate now

     

Profile ID: LFUS-PAI-O-1752355

  Search
All data on this website is collected from public sources. Our data reflects the most accurate information available at the time of publication.