-
2
-
-
26444452720
-
Release of segregated radionuclides from spent fuel
-
L.H. Johnson, J.C. Tait, Release of segregated radionuclides from spent fuel, SKB Technical Report 97-18 (1997).
-
(1997)
SKB Technical Report
, vol.97
, Issue.18
-
-
Johnson, L.H.1
Tait, J.C.2
-
3
-
-
33646557073
-
Synthesis on the long-term behavior of the spent nuclear fuel
-
Poinssot, C.P. Toulhoat, J-P. Grouiller, J. Pavageau, J-P. Piron, M. Pelletier, P. Dehaudt, C. Capellaere, R. Limon, L. Desgranges, C. Jegou, C. Corbel, S. Maillard, M-H. Fauré, J-C. Cicariello, M. Masson, Synthesis on the long-term behavior of the spent nuclear fuel, Vol. 1. CEA Report CEA-R-5958(E) (2001), p. 304.
-
(2001)
CEA Report
, vol.1 CEA-R-5958E
, pp. 304
-
-
Poinssot1
Toulhoat, C.P.2
Grouiller, J.-P.3
Pavageau, J.4
Piron, J.-P.5
Pelletier, M.6
Dehaudt, P.7
Capellaere, C.8
Limon, R.9
Desgranges, L.10
Jegou, C.11
Corbel, C.12
Maillard, S.13
Fauré, M.-H.14
Cicariello, J.-C.15
Masson, M.16
-
5
-
-
12944254323
-
-
Oversby, Werme (Eds.), Scientific Basis for Nuclear Waste Management XXVII
-
C. Ferry, P. Lovera, C. Poinssot, L. Johnson, in: Oversby, Werme (Eds.), Scientific Basis for Nuclear Waste Management XXVII Mater. Res. Soc. Symp. Proc. 807 (2003), p. 35.
-
(2003)
Mater. Res. Soc. Symp. Proc.
, vol.807
, pp. 35
-
-
Ferry, C.1
Lovera, P.2
Poinssot, C.3
Johnson, L.4
-
6
-
-
26444486472
-
-
Pembroke, Ont., Canada, 28 April-1 May 1992, IAEA-TECDOC-697
-
K. Kamimura, in: Proceedings of the Technical Committee Meeting on Fission Gas Release and Fuel Rod Chemistry Related to Extended Burnup, Pembroke, Ont., Canada, 28 April-1 May 1992, IAEA-TECDOC-697 (1992), p. 82.
-
(1992)
Proceedings of the Technical Committee Meeting on Fission Gas Release and Fuel Rod Chemistry Related to Extended Burnup
, pp. 82
-
-
Kamimura, K.1
-
7
-
-
0346406240
-
-
West Palm Beach, Florida, 17-21 April
-
G. Vesterlund, L.V. Corsetti, in: Proceedings of the 1994 International Topical Meeting on Light Water Reactor Fuel Performance, West Palm Beach, Florida, 17-21 April, p. 62.
-
Proceedings of the 1994 International Topical Meeting on Light Water Reactor Fuel Performance
, pp. 62
-
-
Vesterlund, G.1
Corsetti, L.V.2
-
8
-
-
26444473677
-
-
Advances in Fuel Pellet Technology for Improved Performance at High Burnup, IAEA-TECDOC-1036 (1998) Tokyo, 28 October-1 November IAEA, Vienna
-
J. Spino, in: Advances in Fuel Pellet Technology for Improved Performance at High Burnup, IAEA-TECDOC-1036 (1998), Proceedings of the Technical Committee Meeting, Tokyo, 28 October-1 November, 1996, IAEA, Vienna.
-
(1996)
Proceedings of the Technical Committee Meeting
-
-
Spino, J.1
-
10
-
-
26444521747
-
-
Park City
-
Ph. Garcia, A. Bouloré, Y. Guérin, M. Trotabas, P. Goeuriot, P, in: Proceedings of the ANS (2000), Park City.
-
(2000)
Proceedings of the ANS
-
-
Garcia, Ph.1
Bouloré, A.2
Guérin, Y.3
Trotabas, M.4
Goeuriot, P.5
-
11
-
-
0009852748
-
The disposal of Canada's nuclear fuel waste: A study of postclosure safety of in-room emplacement of used CANDU fuel in copper canisters in permeable plutonic rock
-
COG-95-552-2
-
L.H. Johnson, D.M. Leneveu, F. King, D.W. Shoesmith, M. Kolar, D.W Oscarson, S. Sunder, C. Onofrei, J.L. Crosthwaite, The disposal of Canada's nuclear fuel waste: a study of postclosure safety of in-room emplacement of used CANDU fuel in copper canisters in permeable plutonic rock, Volume 2: Vault model Atomic Energy of Canada Limited Report AECL-11494-2, COG-95-552-2 (1996).
-
(1996)
Vault Model Atomic Energy of Canada Limited Report
, vol.2 AECL-11494-2
-
-
Johnson, L.H.1
Leneveu, D.M.2
King, F.3
Shoesmith, D.W.4
Kolar, M.5
Oscarson, D.W.6
Sunder, S.7
Onofrei, C.8
Crosthwaite, J.L.9
-
13
-
-
0011928752
-
An evaluation of results from the experimental programme performed in the Studsvik Hot Cell Laboratory
-
The SKB Spent Fuel Corrosion Programme
-
R.S. Forsyth, The SKB Spent Fuel Corrosion Programme. An evaluation of results from the experimental programme performed in the Studsvik Hot Cell Laboratory, SKB Technical Report 97-25 (1997).
-
(1997)
SKB Technical Report
, vol.97
, Issue.25
-
-
Forsyth, R.S.1
-
14
-
-
0033337226
-
-
D.J. Wronkewiecz, J.H. Lee (Eds.), Scientific Basis for Nuclear Waste Management XXII
-
W.J. Gray, in: D.J. Wronkewiecz, J.H. Lee (Eds.), Scientific Basis for Nuclear Waste Management XXII, Mater. Res. Soc. Symp. Proc. 556 (1999), p. 487.
-
(1999)
Mater. Res. Soc. Symp. Proc.
, vol.556
, pp. 487
-
-
Gray, W.J.1
-
15
-
-
26444442498
-
Spent fuel performance data: An analysis of data relevant to the NNWSI project
-
V.M. Oversby, H.F. Shaw, Spent fuel performance data: an analysis of data relevant to the NNWSI project, Lawrence Livermore National Laboratory Report UCID-20926 (1987).
-
(1987)
Lawrence Livermore National Laboratory Report
, vol.UCID-20926
-
-
Oversby, V.M.1
Shaw, H.F.2
-
16
-
-
24744440809
-
-
M.J. Apted, R.E. Westerman (Eds.), Scientific Basis for Nuclear Waste Management XI
-
C.N. Wilson, in: M.J. Apted, R.E. Westerman (Eds.), Scientific Basis for Nuclear Waste Management XI, Mater. Res. Soc. Symp. Proc. 112 (1988), p. 473.
-
(1988)
Mater. Res. Soc. Symp. Proc.
, vol.112
, pp. 473
-
-
Wilson, C.N.1
-
17
-
-
0023565577
-
-
J.D. Bates, W.B. Seefeldt (Eds.), Scientific Basis for Nuclear Waste Management X
-
C.N. Wilson, H.F. Shaw, in: J.D. Bates, W.B. Seefeldt (Eds.), Scientific Basis for Nuclear Waste Management X, Mater. Res. Soc. Symp. Proc. 84 (1987), p. 123.
-
(1987)
Mater. Res. Soc. Symp. Proc.
, vol.84
, pp. 123
-
-
Wilson, C.N.1
Shaw, H.F.2
-
19
-
-
84909880128
-
-
M.J. Apted, R.E. Westerman (Eds.), Scientific Basis for Nuclear Waste Management XI
-
W.I. Neal, S.A. Rawson, W.M. Murphy, in: M.J. Apted, R.E. Westerman (Eds.), Scientific Basis for Nuclear Waste Management XI, Mater. Res. Soc. Symp. Proc. 112 (1988), p. 505.
-
(1988)
Mater. Res. Soc. Symp. Proc.
, vol.112
, pp. 505
-
-
Neal, W.I.1
Rawson, S.A.2
Murphy, W.M.3
-
20
-
-
0345279650
-
Source term for peformance assessment of spent fuel as a waste form
-
B. Grambow, A. Loida, A. Martinez-Esparza, P. Diaz-Arocas, J. De Pablo, J.-L. Paul, G. Marx, J.-P. Glatz, K. Lemmens, K. Ollila, H. Christensen, Source term for peformance assessment of spent fuel as a waste form. European Commission Report EUR 19140 EN (2000).
-
(2000)
European Commission Report EUR 19140 en
-
-
Grambow, B.1
Loida, A.2
Martinez-Esparza, A.3
Diaz-Arocas, P.4
De Pablo, J.5
Paul, J.-L.6
Marx, G.7
Glatz, J.-P.8
Lemmens, K.9
Ollila, K.10
Christensen, H.11
-
25
-
-
26444477457
-
Synthesis report on the relevant diffusion coefficients of fission products and helium in spent nuclear fuels
-
P. Lovera, C. Ferry, C. Poinssot, L.H. Johnson, Synthesis report on the relevant diffusion coefficients of fission products and helium in spent nuclear fuels, CEA-Report CEA-R-6039 (2003).
-
(2003)
CEA-report
, vol.CEA-R-6039
-
-
Lovera, P.1
Ferry, C.2
Poinssot, C.3
Johnson, L.H.4
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