UO2 MATRIX DISSOLUTION RATES AND GRAIN BOUNDARY INVENTORIES OF Cs, Sr, AND Tc IN SPENT LWR FUEL

UO2 MATRIX DISSOLUTION RATES AND GRAIN BOUNDARY INVENTORIES OF Cs, Sr, AND Tc IN SPENT LWR FUEL

Author(s):

Publication title:

Scientific basis for nuclear waste management XIV : symposium held November 26-29, 1990, Boston, Massachusetts, U.S.A.

Title of ser.:

Materials Research Society symposium proceedings

Ser. no.:

212

Pub. Year:

1991

Page(from):

205

Page(to):

212

Pages:

8

Pub. info.:

Pittsburgh, Pa.: Materials Research Society

ISSN:

02729172

ISBN:

9781558991040 [1558991042]

Language:

English

Call no.:

M23500/212

Type:

Conference Proceedings

Details

TDL ID:	ZA00015696
Series ID:	PA00000011
Conf. info. (Name):	Symposium on scientific basis for nuclear waste management
Conf. info. (Number):	16th
Conf. info. (Venue):	Boston, MA, USA
Conf. info. (Date):	1990.11.26-1990.11.29

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