Radiation shielded enclosure for spent nuclear fuel cask

Patent metadata

Field	Value
Publication number	US-11798699-B2
Application number	US-202217979405-A
Country	US
Kind code	B2
Filing date	Nov 2, 2022
Priority date	Aug 23, 2019
Publication date	Oct 24, 2023
Grant date	Oct 24, 2023

Abstract

A containment enclosure for shielding an outer cask containing an inner canister loaded with nuclear waste such as spent fuel rods. The enclosure includes a lower base portion at least partially embedded in a concrete pad and an upper radiation shielding portion defined by a shield jacket coupled to and supported by the lower base portion at a circumferential joint. Cavities of the base and shielding portions collectively define a contiguous containment space for the cask. A portion of the cask resides in each of the base and shielding portions which completely enclose and shield the cask to minimize radiation dosage of personnel in the environment surrounding the cask. The cask is cooled by a natural convectively-driven ambient cooling air ventilation system including air inlets at the circumferential joint of the enclosure. The concrete pad may be part of a spent nuclear fuel storage installation comprising plural cask containment enclosures.

First claim

What is claimed is:

1. A method for providing radiation shielding for a cask containing a nuclear waste canister, the method comprising:
at least partially embedding an upwardly open base portion in a concrete pad;
lowering the cask into the upwardly open lower cavity of the base portion;
positioning a shield jacket over the cask; and
abuttingly engaging the shield jacket with the base portion forming a circumferential joint therebetween;
wherein the cask is fully enclosed by the shield jacket and base portion.

2. The method according to claim 1 , wherein the abuttingly engaging step further includes compressing a gasket between the base portion and shield jacket at the circumferential joint.

3. The method according to claim 2 , wherein the gasket is spaced radially inwards from outer surfaces of the shield jacket and base portion at the circumferential joint, and further comprising welding the outer surfaces of the shield jacket to the base portion at the circumferential joint.

4. The method according to claim 1 , wherein a plurality of circumferentially spaced apart and laterally open cooling air inlets are formed at the circumferential joint by the abuttingly engaging step.

5. The method according to claim 4 , wherein the air inlets are defined by open areas of a castellated skirt attached to a bottom end of the shield jacket.

6. The method according to claim 4 , wherein the air inlets are disposed proximal to grade defined by a top surface of the concrete pad, and distal to a top of the shield jacket.

7. The method according to claim 4 , wherein the abuttingly engaging step further forms an inwardly recessed annular plenum at the circumferential joint.

8. The method according to claim 1 , wherein the air inlets are in direct fluid communication with a top portion of a peripheral annular downcomer in the base portion, the downcomer in fluid communication with the lower cavity of base portion via a plurality of circumferentially spaced air exchange passages formed radially through an innermost shell of the base portion.

9. The method according to claim 1 , wherein the lowering step results in e cask protruding upwards out of the lower cavity of the base portion.

10. The method according to claim 1 , wherein the shield jacket comprises a boron-containing radiation blocking material.

11. The method according to claim 10 , wherein the radiation blocking material is sandwicl ed between a pair of metal shells.

12. The method according to claim 11 , wherein the shield jacket comprises a frustoconical section coupled to a cylindrical section which abuttingly engages the base portion.

Assignees

• Holtec International

Inventors

• Singh Krishna P

Classifications

• G21F9/34 Primary

  Disposal of solid waste · CPC title

• G21F1/125

  comprising metals · CPC title

• G21F5/008 Primary

  Containers for fuel elements · CPC title

• G21F5/10

  Heat-removal systems, e.g. using circulating fluid or cooling fins · CPC title

• G21F5/12

  Closures for containers; Sealing arrangements · CPC title