-
4
-
-
43049169667
-
-
Determination of Research Reactor Fuel Burnup, IAEA-TECDOC-633, January 1992.
-
Determination of Research Reactor Fuel Burnup, IAEA-TECDOC-633, January 1992.
-
-
-
-
5
-
-
43049173002
-
-
137Cs) gamma-ray intensity ratio as a burn-up monitor for LWR fuels, in: Sixth International Conference on Nuclear Criticality Safety, ICNP'99, Versailles, France, 20-24 September 1999.
-
137Cs) gamma-ray intensity ratio as a burn-up monitor for LWR fuels, in: Sixth International Conference on Nuclear Criticality Safety, ICNP'99, Versailles, France, 20-24 September 1999.
-
-
-
-
12
-
-
33745593739
-
-
Murphy M., Jatuff F., Grimm P., Seiler R., Brogli R., Meier G., Berger H., and Chawla R. Ann. Nucl. En. 33 (2006) 760
-
(2006)
Ann. Nucl. En.
, vol.33
, pp. 760
-
-
Murphy, M.1
Jatuff, F.2
Grimm, P.3
Seiler, R.4
Brogli, R.5
Meier, G.6
Berger, H.7
Chawla, R.8
-
13
-
-
43049157297
-
-
DSPEC™, Digital Gamma-Ray Spectrometer, EG&G ORTEC Catalog, Oak Ridge.
-
DSPEC™, Digital Gamma-Ray Spectrometer, EG&G ORTEC Catalog, Oak Ridge.
-
-
-
-
14
-
-
43049173001
-
-
® 95 and Microsoft Windows NT, A66-B32 Software User's Manual, EG&G ORTEC Part No. 774780, Manual Revision A, Oak Ridge.
-
® 95 and Microsoft Windows NT, A66-B32 Software User's Manual, EG&G ORTEC Part No. 774780, Manual Revision A, Oak Ridge.
-
-
-
-
15
-
-
43049174351
-
-
S. Caruso, Characterisation of High-Burnup LWR Fuel Rods through Gamma Tomography, Thèse EPFL (Ecole Polytechnique Federale de Lausanne) No. 3762, 2007 (http://library.epfl.ch/theses/?nr=3762).
-
S. Caruso, Characterisation of High-Burnup LWR Fuel Rods through Gamma Tomography, Thèse EPFL (Ecole Polytechnique Federale de Lausanne) No. 3762, 2007 (http://library.epfl.ch/theses/?nr=3762).
-
-
-
-
16
-
-
43049155718
-
-
A Combinatorial Geometry Version of QAD-P54, a Point Kernel Code System for Neutron and Gamma-Ray Shielding Calculations Using the GP Buildup Factor, 1977, CCC-493/QAD-CGGP, RSIC Computer Code Collection, Radiation Shielding Information Center, Oak Ridge National Laboratory.
-
A Combinatorial Geometry Version of QAD-P54, a Point Kernel Code System for Neutron and Gamma-Ray Shielding Calculations Using the GP Buildup Factor, 1977, CCC-493/QAD-CGGP, RSIC Computer Code Collection, Radiation Shielding Information Center, Oak Ridge National Laboratory.
-
-
-
-
20
-
-
43049154157
-
-
J.A. Fessler, Aspire 3.0 user's guide: a sparse iterative reconstruction library. Technical Report No. 293, Communications & Signal Processing Laboratory, University of Michigan, 2001.
-
J.A. Fessler, Aspire 3.0 user's guide: a sparse iterative reconstruction library. Technical Report No. 293, Communications & Signal Processing Laboratory, University of Michigan, 2001.
-
-
-
-
21
-
-
43049160430
-
-
J.F. Briesmeister, MCNP-A general Monte Carlo N-particle transport code, version 4B, Los Alamos Report LA-12625-M, 1997.
-
J.F. Briesmeister, MCNP-A general Monte Carlo N-particle transport code, version 4B, Los Alamos Report LA-12625-M, 1997.
-
-
-
-
22
-
-
43049177494
-
-
S.T. Hsue, T.W. Crane, W.L. Talbert, J.C. Lee, Nondestructive assay methods for irradiated nuclear fuels, Los Alamos Internal Report LA-6923, 1978.
-
S.T. Hsue, T.W. Crane, W.L. Talbert, J.C. Lee, Nondestructive assay methods for irradiated nuclear fuels, Los Alamos Internal Report LA-6923, 1978.
-
-
-
-
23
-
-
43049155717
-
-
ENDF/B-VI nuclear data library.
-
ENDF/B-VI nuclear data library.
-
-
-
|