Nuclear reactor heat pipe

• US 5,684,848 A
• Filed: 05/06/1996
• Issued: 11/04/1997
• Est. Priority Date: 05/06/1996
• Status: Expired due to Fees

• Current Assignee: General Electric Company
• Original Assignee: General Electric Company
• Inventors: Fennern, Larry Edgar, Gou, Perng-Fei, Sawyer, Craig Delany
• Primary Examiner(s): Wasil, Daniel D.
• Application Number:
  US08/643,802
• Time in Patent Office: 547 Days
• Field of Search: 376/367, 376/298, 165/104.26, 165/272, 165/104.21
• US Class Current: 376/367
• CPC Class Codes: F28D 15/0275 Arrangements for coupling heat-pipes together or with other structures, e.g. with base blocks; Heat pipe cores
• CPC Class Codes: F28D 15/04 with tubes having a capillary structure
• CPC Class Codes: F28D 2021/0054 for nuclear applications cooling arrangements for nuclear reactors G21C15/00
• CPC Class Codes: G21C 15/00 Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
• CPC Class Codes: G21C 15/257 using heat-pipes in general F28D, F28F
• CPC Class Codes: Y02E 30/30 Nuclear fission reactors

Abstract

A nuclear reactor including a heat pipe for transferring heat from the reactor pressure vessel to a steam supply vessel is described. More particularly, in one embodiment, the heat pipe includes an evaporator section positioned in the reactor vessel, a condenser section positioned in the steam supply vessel, and an adiabatic section extending between and in flow communication with the evaporator section and the condenser section. The adiabatic section of the heat pipe includes a substantially cylindrical outer sleeve and a substantially cylindrical inner sleeve. An annulus region is formed between the inner and outer sleeves and the annulus region is in flow communication with the steam supply vessel. An insulating layer covers an inner wall of the outer sleeve. A substantially annular wick member is positioned adjacent an inner wall of the inner sleeve, and a steam path is defined by an inner face of the wick member.

Claims

1. A nuclear reactor, comprising:

a reactor vessel having a plurality of fuel rods positioned therein; and

a heat pipe comprising;

an evaporator section positioned in said reactor vessel;

a condenser section positioned outside said reactor vessel; and

an adiabatic section extending between and in communication with said evaporator section and said condenser section, said adiabatic section comprising a substantially cylindrical outer sleeve and a substantially annular wick member positioned within said sleeve, said adiabatic section further comprising a substantially cylindrical inner sleeve positioned within said outer sleeve, an annulus region between said inner sleeve and said outer sleeve, and said wick member, located adjacent an inner wall of said inner sleeve.

2. A nuclear reactor in accordance with claim 1 further comprising a steam supply system comprising a steam supply vessel, said condenser section positioned in said steam supply vessel.

3. A nuclear reactor in accordance with claim 1 wherein said steam supply vessel comprises a feedwater inlet and a steam outlet.

4. A nuclear reactor in accordance with claim 1 wherein said adiabatic section further comprises an insulating layer covering an inner wall of said outer sleeve.

5. A nuclear reactor in accordance with claim 4 further comprising a steam supply system comprising a steam supply vessel, said heat pipe condenser section positioned in said steam supply vessel, said heat pipe annulus region in flow communication with said steam supply vessel.

6. A nuclear reactor in accordance with claim 1 wherein said evaporator section comprises a plurality of elongate tubes having a substantially cylindrical shape, each of said tubes having a substantially cylindrical wick member extending therethrough.

7. A nuclear reactor in accordance with claim 1 wherein said condenser section comprises a plurality of elongate tubes having a substantially cylindrical shape, each of said tubes having a substantially cylindrical wick member extending therethrough.

8. A heat pipe for transferring heat energy from a nuclear reactor vessel to a steam supply system vessel, said heat pipe comprising:

an evaporator section for being positioned in the reactor vessel;

a condenser section for being positioned in the steam supply vessel; and

an adiabatic section extending between and in flow communication with said evaporator section and said condenser section said adiabatic section comprising a substantially cylindrical outer sleeve and a substantially annular wick member positioned within said sleeve, said adiabatic section further comprising a substantially cylindrical inner sleeve positioned within said outer sleeve, an annulus region between said inner sleeve and said outer sleeve, and said wick member located adjacent an inner wall of said inner sleeve.

9. A heat pipe in accordance with claim 8 wherein said adiabatic section further comprises an insulating layer covering an inner wall of said outer sleeve.

10. A heat pipe in accordance with claim 9 wherein said annulus region is positionable for being in flow communication with the steam supply vessel.

11. A heat pipe in accordance with claim 8 wherein said evaporator section comprises a plurality of elongate tubes having a substantially cylindrical shape, each of said tubes having a substantially cylindrical wick member extending therethrough.

12. A heat pipe in accordance with claim 8 wherein said condenser section comprises a plurality of elongate tubes having a substantially cylindrical shape, each of said tubes having a substantially cylindrical wick member extending therethrough.