-
1
-
-
32044468382
-
Performance of advanced fuel materials for high burnup
-
Würzburg, Germany, March 16-19
-
Y. Tsukuda, Y. Kosaka, T. Kido, et al., “Performance of advanced fuel materials for high burnup,” ENS TOPFUEL’03, Würzburg, Germany, March 16-19, 2003, (2003).
-
(2003)
ENS TOPFUEL’03
, pp. 2003
-
-
Tsukuda, Y.1
Kosaka, Y.2
Kido, T.3
-
2
-
-
33750411258
-
Programa de Extension de Irradiacion en CN Vandellos II
-
Alicante, Spain, Sept
-
J. J. Serna, G. Rubio, P. Gonzalez, “Programa de Extension de Irradiacion en CN Vandellos II,” 30“Reunion Anual de la SNE, Alicante, Spain, Sept. 2004, (2004).
-
(2004)
30“Reunion Anual De La SNE
, pp. 2004
-
-
Serna, J.J.1
Rubio, G.2
Gonzalez, P.3
-
3
-
-
33750400263
-
NUPEC PWR Fuel irradiation programme on advanced materials for high burnup
-
Storefjell, Norway, Sept. 8-13
-
N. Kono, “NUPEC PWR Fuel irradiation programme on advanced materials for high burnup,” Halden EHPG Meeting, Storefjell, Norway, Sept. 8-13, 2002, (2002).
-
(2002)
Halden EHPG Meeting
, pp. 2002
-
-
Kono, N.1
-
4
-
-
85010507788
-
Irradiation Extension Program in CN Vandellos II
-
Granada, Spain, Nov
-
a Reunion Anual SNE. Granada, Spain, Nov. 1999, (1999).
-
(1999)
a Reunion Anual SNE
, pp. 1999
-
-
Serna, J.J.1
Goto, K.2
Abeta, S.3
Filella, J.M.4
-
5
-
-
8844248639
-
Quantitative assessment of irradiation effect on creep and corrosion properties of Zr-base alloys
-
T. Kido, Y. Senda, Y. Tukuta, et al., “Quantitative assessment of irradiation effect on creep and corrosion properties of Zr-base alloys,” Zirconium in the Nuclear Industry: Thirteenth International Symposium, ASTM STP 1423, p. 780-795 (2002).
-
(2002)
Zirconium in the Nuclear Industry: Thirteenth International Symposium, ASTM STP
, vol.1423
, pp. 780-795
-
-
Kido, T.1
Senda, Y.2
Tukuta, Y.3
-
6
-
-
31144450572
-
Segmented fuel irradiation program investigation on advanced materials
-
Avignon, France, Sept
-
H. Uchida, K. Goto, R. Sabate, et al., “Segmented fuel irradiation program investigation on advanced materials, ENS TOPFUEL’99. Avignon, France, Sept. 1999, (1999).
-
(1999)
ENS TOPFUEL’99
, pp. 1999
-
-
Uchida, H.1
Goto, K.2
Sabate, R.3
-
7
-
-
33750421196
-
Segmented fuel rod irradiation program on advanced materials for high burnup
-
Park City, Utah, USA, April
-
Y. Irisa, K. Murai, K. Goto, et al., “Segmented fuel rod irradiation program on advanced materials for high burnup, ANS Int. Conf. on Light Water Reactor Fuel Performance, Park City, Utah, USA, April 2000, (2000).
-
(2000)
ANS Int. Conf. on Light Water Reactor Fuel Performance
, pp. 2000
-
-
Irisa, Y.1
Murai, K.2
Goto, K.3
-
8
-
-
28344443889
-
Puzzling features of EPMA radial fission gas release profiles: The key to realistic modelling of fission gas release up to ultra high burnup of 100MWD/kgM with CARO-E
-
Windermere, UK, June
-
F. Sontheimer, H. K. Landskron, “Puzzling features of EPMA radial fission gas release profiles: The key to realistic modelling of fission gas release up to ultra high burnup of 100MWD/kgM with CARO-E,” IAEA TCM on Nuclear Fuel Behaviour Modelling at High Burnup And Its Experimental Support, Windermere, UK, June 2000, (2000).
-
(2000)
IAEA TCM on Nuclear Fuel Behaviour Modelling at High Burnup and Its Experimental Support
, pp. 2000
-
-
Sontheimer, F.1
Landskron, H.K.2
-
9
-
-
2642540569
-
Contribution of the RIM to the overall fission gas release: What do isotopic analyses reveal
-
Cadarache, France, Sept. 26-29
-
J. Noirot, L. Desgranges, P. Marimbeau, “Contribution of the RIM to the overall fission gas release: what do isotopic analyses reveal,” Semin. on FGR Behaviour in Water Reactor Fuels, Cadarache, France, Sept. 26-29, 2000, (2000).
-
(2000)
Semin. on FGR Behaviour in Water Reactor Fuels
, pp. 2000
-
-
Noirot, J.1
Desgranges, L.2
Marimbeau, P.3
-
10
-
-
85010507758
-
Fission gas release in ABB SVEA 10x 10 BWR fuel
-
Portland, Oregon, USA, March 2-6
-
D. Schrire, I. Matsson, B. Grapengiesser, “Fission gas release in ABB SVEA 10x 10 BWR fuel,” ANS Int. Topical Meeting on Light Water Reactor Fuel Performance, Portland, Oregon, USA, March 2-6, 1997, (1997).
-
(1997)
ANS Int. Topical Meeting on Light Water Reactor Fuel Performance
, pp. 1997
-
-
Schrire, D.1
Matsson, I.2
Grapengiesser, B.3
-
11
-
-
33750411755
-
Fission gas release and fuel swelling at burnups higher than 50MWd/kgU
-
Cadarache, France, Sept. 26-29
-
S. Bremier, R. Manzel, C. T. Walker, “Fission gas release and fuel swelling at burnups higher than 50MWd/kgU,” Semin. on FGR Behaviour in Water Reactor Fuels, Cadarache, France, Sept. 26-29, 2000, (2000).
-
(2000)
Semin. on FGR Behaviour in Water Reactor Fuels
, pp. 2000
-
-
Bremier, S.1
Manzel, R.2
Walker, C.T.3
-
12
-
-
33750410302
-
-
Appendix A [“Improvements to the MATPRO Library of Materials Properties (Properties Related to High Burnup Fuel)“] of INEEL/EXT-02-00589, Rev. 2.2
-
S. Bremier, R. Manzel, C. T. Walker, SCDAP/RELAP5-3D Code Manual Volume 4: MATPRO—A Library of Materials Properties for Light-Water-Reactor Accident Analysis, Appendix A [“Improvements to the MATPRO Library of Materials Properties (Properties Related to High Burnup Fuel)“] of INEEL/EXT-02-00589, Rev. 2.2, (2003).
-
(2003)
SCDAP/RELAP5-3D Code Manual Volume 4: MATPRO—A Library of Materials Properties for Light-Water-Reactor Accident Analysis
-
-
Bremier, S.1
Manzel, R.2
Walker, C.T.3
|