Patent · US Expired

On-site concrete cask storage system for spent nuclear fuel

US4800062A · kind A · utility

60Cited by
4References
8Claims
0Family size

Assignee

Inventors

Key dates

Filing dateFeb 23, 1987
Grant dateJan 24, 1989
Priority date
Expiry dateFeb 23, 2007

Classification

  • Technology area (CPC Y)Emerging Cross-Sectional Technologies
  • CPC primaryY02E30/30
  • WIPO fieldEngines, pumps, turbines
  • WIPO sectorMechanical engineering

Abstract

A storage system for storing spent nuclear fuel on site at a reactor complex includes a concrete storage cask adapted to receive fuel assemblies or loaded fuel canisters from the spent-fuel pool. The storage cask is sealed and maintained on site for a predetermined time period. The fuel assemblies or canisters can then be transferred from the concrete storage cask to a shipping container for shipment to a permanent disposal site, while the concrete casks can be reused or broken up so that the concrete can be used as fill or ballast. The fuel assemblies or canisters are removed from the pool and placed in the cask in a dry condition. Alternatively, the cask may be submerged in the fuel pool for loading. Preferably, the cask is sealed and backfilled with an inert gas. In one embodiment of the invention, the concrete storage cask is manufactured on site at the reactor complex.

Source: USPTO / EPO open patent data. Objective bibliographic and citation counts.