Databank

POSIVA Report 1996-10

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Name:

Gamma and Neutron Dose Rates on the Outer Surface of the Nuclear Waste Disposal Canisters

Writer:

Markku Anttila

Language:

English

Page count:

39

ISBN:

951-652-009-X; 1239-3096

Summary:

Working report: GAMMA AND NEUTRON DOSE RATES ON THE OUTER SURFACE OF THE NUCLEAR
WASTE DISPOSAL CANISTERS




Gamma and neutron dose rates on the outer surface of the new versions of the canisters designed
for the final disposal of the Finnish spent nuclear fuel have been calculated with the MCNP4A
code based on the Monte Carlo technique and with the MARMER code, which applies the
standard point-kernel method. The gamma dose rates calculated by the programs are in a
satisfactory agreement.

Two canister types, one for hexagonal VVER-440 fuel assemblies from the Loviisa nuclear power
plant ("IVO canister") and the other for square BWR fuel bundles from the Olkiluoto nuclear
power plant ("TVO canister") have been studied. The canister types are quite similar.

The maximum gamma dose rate on the outer surface of the IVO canister designed to contain
11 VVER-440 fuel assemblies is about 250 mSv/h, when the discharge burnup of the spent fuel is
42 MWd/kgU and the cooling time 20 years. For the TVO canister loaded with 11 BWR fuel
bundles having the discharge burnup of 45 MWd/kgU and having cooled for 20 years, the
corresponding value is about 150 mSv/h. In both cases the average dose rates are about one half of
the maximum values.

The neutron dose rates around the canisters are much lower than the gamma dose rates, typically
less than 10 mSv/h.
GAMMA AND NEUTRON DOSE RATES ON THE OUTER SURFACE OF THE NUCLEAR
WASTE DISPOSAL CANISTERS




Gamma and neutron dose rates on the outer surface of the new versions of the canisters designed
for the final disposal of the Finnish spent nuclear fuel have been calculated with the MCNP4A
code based on the Monte Carlo technique and with the MARMER code, which applies the
standard point-kernel method. The gamma dose rates calculated by the programs are in a
satisfactory agreement.

Two canister types, one for hexagonal VVER-440 fuel assemblies from the Loviisa nuclear power
plant ("IVO canister") and the other for square BWR fuel bundles from the Olkiluoto nuclear
power plant ("TVO canister") have been studied. The canister types are quite similar.

The maximum gamma dose rate on the outer surface of the IVO canister designed to contain
11 VVER-440 fuel assemblies is about 250 mSv/h, when the discharge burnup of the spent fuel is
42 MWd/kgU and the cooling time 20 years. For the TVO canister loaded with 11 BWR fuel
bundles having the discharge burnup of 45 MWd/kgU and having cooled for 20 years, the
corresponding value is about 150 mSv/h. In both cases the average dose rates are about one half of
the maximum values.

The neutron dose rates around the canisters are much lower than the gamma dose rates, typically
less than 10 mSv/h.

Keywords:

File(s):

Gamma and Neutron Dose Rates on the Outer Surface of the Nuclear Waste Disposal Canisters (pdf) (537.8 KB)


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