Pressurizer heater for the primary cooling system of a pressurized-water nuclear reactor

Patent metadata

Field	Value
Publication number	US-9730277-B2
Application number	US-9717006-A
Country	US
Kind code	B2
Filing date	Dec 12, 2006
Priority date	Dec 16, 2005
Publication date	Aug 8, 2017
Grant date	Aug 8, 2017

Abstract

The invention relates to a heating rod for a pressurizer of a primary cooling system of a pressurized-water nuclear reactor, the rod comprising a metal outer shell ( 36 ) of longitudinally elongate shape having an external surface ( 62 ), and a heating element ( 40 ) mounted inside the shell ( 36 ). It comprises an anti-corrosion coating ( 60 ) covering at least part of the external surface ( 62 ) of the shell ( 36 ).

First claim

The invention claimed is:

1. A heating rod in a pressurizer of a primary cooling system of a pressurized-water nuclear reactor, the pressurizer containing a primary liquid, the heating rod comprising:
an outer shell made of stainless steel or alloy of longitudinally elongate shape having an external surface, wherein the external surface continues as one piece;
a heating element mounted inside the outer shell so that an immersed portion of the rod has a heating longitudinal section and non-heating longitudinal sections located both above and below the heating longitudinal section; and
an anti-corrosion coating covering a part of the external surface of the outer shell, the coating covering completely the external surface along the whole of the heating longitudinal section and continuing longitudinally on each side of the heating longitudinal section over a guard zone distance along the non heating longitudinal sections, other areas of the external surface along the non heating longitudinal sections zone being non coated by the anti-corrosion coating;
such that the external surface is not in contact with the primary liquid along the heating longitudinal section and is partially in contact with the primary liquid along the non heating longitudinal sections;
wherein the coating predominantly comprises nickel.

2. The rod according to claim 1 , wherein the coating comprises at least 95% by weight nickel.

3. The rod according to claim 1 , wherein the coating has been deposited on the external surface by electrolysis in a bath of nickel salts.

4. The rod according to claim 1 , wherein the coating has a thickness greater than 50 micrometers.

5. The rod according to claim 1 , wherein the guard zone distance is greater than 10 millimeters.

6. The rod according to claim 1 , wherein the outer shell is made of austenitic stainless steel.

7. The heating rod to claim 1 , wherein the outer shell is tubular.

8. The heating rod to claim 1 , wherein the heating element is enclosed in the outer shell.

9. The heating rod to claim 1 , wherein the outer shell is the most exterior element of the heating rod.

Assignees

• Steltzlen Françoise
• Foucault Marc
• Meyzaud Yves
• Scott Peter
• Areva Np

Inventors

• Steltzlen Françoise
• Foucault Marc
• Meyzaud Yves
• Scott Peter

Classifications

• Y02E30/30

  Nuclear fission reactors · CPC title

• C25D7/04

  Tubes; Rings; Hollow bodies · CPC title

• G21C1/09

  Pressure regulating arrangements, i.e. pressurisers · CPC title

• C25D3/12

  of nickel or cobalt · CPC title

• Y02E30/40

  Cross-Sectional Technologies · mapped topic