| Future of nuclear energy and the role of nuclear data | p. 3 |
| Nuclear data needs for generation IV nuclear energy systems-summary of U.S. workshop | p. 8 |
| Nuclear data needs for the assessment of Gen. IV systems | p. 18 |
| Nuclear data needs for generation IV - lessons from benchmarks | p. 32 |
| Core design issues of the supercritical water fast reactor | p. 38 |
| GFR core neutronics studies at CEA | p. 46 |
| Comparative study on different phonon frequency spectra of graphite in GCR | p. 58 |
| Innovative fuel types for minor actinides transmutation | p. 64 |
| The importance of nuclear data in modeling and designing generation IV fast reactors | p. 70 |
| The GIF and Mexico- "everything is possible" | p. 72 |
| Sensitivity of advanced reactor and fuel cycle performance parameters to nuclear data uncertainties | p. 81 |
| Sensitivity and uncertainty study for thermal molten salt reactors | p. 101 |
| Integral reactor physics benchmarks- the international criticality safety benchmark evaluation project (ICSBEP) and the international reactor physics experiment evaluation project (IRPHEP) | p. 113 |
| Computer model of an error propagation through micro-campaign of fast neutron gas cooled nuclear reactor | p. 128 |
| Combining differential and integral experiments on [superscript 239]Pu for reducing uncertainties in nuclear data applications | p. 138 |
| Sensitivity of activation cross sections of the hafnium, tanatalum and tungsten stable isotopes to nuclear reaction mechanisms | p. 145 |
| Generating covariance data with nuclear models | p. 153 |
| Sensitivity of candu-SCWR reactors physics calculations to nuclear data files | p. 163 |
| The lead cooled fast reactor benchmark BREST-300 : analysis with sensitivity method | p. 173 |
| Sensitivity analysis of neutron cross-sections considered for design and safety studies of LFR and SFR generation IV systems | p. 183 |
| INL capabilities for nuclear data measurements using the Argonne intense pulsed neutron source facility | p. 195 |
| Cross-section measurements in the fast neutron energy range | p. 208 |
| Recent measurements of neutron capture cross sections for minor actinides by a JNC and Kyoto University group | p. 216 |
| Determination of minor actinides fission cross sections by means of transfer reactions | p. 222 |
| Nuclear data services from the NEA | p. 235 |
| Nuclear databases for energy applications : an IAEA perspective | p. 244 |
| Nuclear data evaluation for generation IV | p. 253 |
| Improved evaluations of neutron-induced reactions on Americium isotopes | p. 262 |
| Using improved ENDF-based nuclear data for Candu reactor calculations | p. 270 |
| A comparative study on the graphite-moderated reactors using different evaluated nuclear data | p. 278 |
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