D.E. Blahnik
Pacific Northwest National Laboratory
5 Papers
157 Citations
D.E. Blahnik is an academic researcher from Pacific Northwest National Laboratory. The author has contributed to research in topics: Spent nuclear fuel & Radioactive waste. The author has an hindex of 4, co-authored 5 publications.
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Papers
Characterization of spent fuel approved testing material: ATM-103
R.J. Guenther,D.E. Blahnik,T.K. Campbell,U.P. Jenquin,J.E. Mendel,L.E. Thomas,C.K. Thornhill +6 more
- 01 Apr 1988
TL;DR: The characterization data obtained to date are described for Approved Testing Material (ATM)-103, which is spent fuel from Assembly D101 of pressurized-water reactor Calvert Cliffs, No. 1 as discussed by the authors.
Characterization of spent fuel approved testing material: ATM-106
R.J. Guenther,D.E. Blahnik,T.K. Campbell,U.P. Jenquin,J.E. Mendel,C.K. Thornhill +5 more
- 01 Oct 1988
TL;DR: The characterization data obtained to date are described for Approved Testing Material (ATM)-106 spent fuel from Assembly BT03 of pressurized-water reactor Calvert Cliffs No. 1 as discussed by the authors.
Characterization of spent fuel approved testing material---ATM-105
R.J. Guenther,D.E. Blahnik,T.K. Campbell,U.P. Jenquin,J.E. Mendel,L.E. Thomas,C.K. Thornhill +6 more
- 01 Dec 1991
TL;DR: The characterization data obtained to data are described for Approved Testing Material 105 (ATM-105), which is spent fuel from Bundles CZ346 and CZ348 of the Cooper Nuclear Power Plant, a boiling-water reactor as mentioned in this paper.
Characterization of spent fuel approved testing material--ATM-104
R.J. Guenther,D.E. Blahnik,U.P. Jenquin,J.E. Mendel,L.E. Thomas,C.K. Thornhill +5 more
- 01 Dec 1991
TL;DR: The characterization data obtained to date are described for Approved Testing Material 104 (ATM-104), which is spent fuel from Assembly DO47 of the Calvert Cliffs Nuclear Power Plant (Unit 1), a pressurized-water reactor as discussed by the authors.
Detailed Characterization of LWR Fuel Rods for the U.S. Civilian Radioactive Waste Management Program
TL;DR: In this article, a light-water reactor (LWR) spent fuel with peak burnups from ∼31 to 46 MWd/kgM and rod-average fission gas releases of ∼0.3 to 11%.
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