Databank

POSIVA Report 1996-13

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Name:

Design Report of the Canister for Nuclear Fuel Disposal

Writer:

Heikki Raiko; Jukka-Pekka Salo

Language:

English

Page count:

56

ISBN:

951-652-012-X; 1239-3096

Summary:

Working report: DESIGN REPORT OF THE CANISTER FOR NUCLEAR FUEL DISPOSAL




The report provides a summary of the design of the canister for final disposal of nuclear fuel. The
canister structure consists of a cylindrical massive nodular graphite cast iron insert covered by a
50 mm thick copper overlay. The capacity of the canister is 11 assemblies of BWR or VVER 440
fuel.

The canister shall be tight with a high probability for about 100 000 years. The good and long
lasting tightness requires:

- good initial tightness, that is achieved by high quality requirements and extensive quality
control,

- good corrosion resistance, which is obtained by the overpack of oxygen free copper and

- mechanical strength of the canister, that is ensured by analyses; the following loads are
considered: hydrostatic pressure, even and uneven swelling pressure of bentonite, thermal
effects, and elevated hydrostatic pressure during glaciation. The allowed stresses and strains
are set in such a way that reasonable engineering safety factors are obtained in all assessed
loading cases.

The canister shall limit the radiation dose rate outside the canister to minimise the radiolysis of the
water in the vicinity of the canister. The canister insert shall keep the fuel assemblies in a
subcritical configuration even if the void in the canister is filled with water due to postulated
leakage.

The design basis of the canister is set, the performed analyses are summarised and the results are
assessed and discussed in the report.
DESIGN REPORT OF THE CANISTER FOR NUCLEAR FUEL DISPOSAL




The report provides a summary of the design of the canister for final disposal of nuclear fuel. The
canister structure consists of a cylindrical massive nodular graphite cast iron insert covered by a
50 mm thick copper overlay. The capacity of the canister is 11 assemblies of BWR or VVER 440
fuel.

The canister shall be tight with a high probability for about 100 000 years. The good and long
lasting tightness requires:

- good initial tightness, that is achieved by high quality requirements and extensive quality
control,

- good corrosion resistance, which is obtained by the overpack of oxygen free copper and

- mechanical strength of the canister, that is ensured by analyses; the following loads are
considered: hydrostatic pressure, even and uneven swelling pressure of bentonite, thermal
effects, and elevated hydrostatic pressure during glaciation. The allowed stresses and strains
are set in such a way that reasonable engineering safety factors are obtained in all assessed
loading cases.

The canister shall limit the radiation dose rate outside the canister to minimise the radiolysis of the
water in the vicinity of the canister. The canister insert shall keep the fuel assemblies in a
subcritical configuration even if the void in the canister is filled with water due to postulated
leakage.

The design basis of the canister is set, the performed analyses are summarised and the results are
assessed and discussed in the report.

Keywords:

File(s):

Design Report of the Canister for Nuclear Fuel Disposal (pdf) (1.2 MB)


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