Nuclear Power Plants
10 tracks • 0 favorites
Chapter8 3 8. Sensitivity and Uncertainty Quantification of Neutronic Integral Data Using ENDF/B-VII.1 and JENDL-4.0 Evaluations
Episodes
Chapter8 3 8. Sensitivity and Uncertainty Quantification of Neutronic Integral Data Using ENDF/B-VII.1 and JENDL-4.0 Evaluations
Chapter8 2 8. Sensitivity and Uncertainty Quantification of Neutronic Integral Data Using ENDF/B-VII.1 and JENDL-4.0 Evaluations
Chapter8 1 8. Sensitivity and Uncertainty Quantification of Neutronic Integral Data Using ENDF/B-VII.1 and JENDL-4.0 Evaluations
Chapter7 5 7. Optimization of Cosmic Radiation Detection in Saline Environment
Chapter7 6 7. Optimization of Cosmic Radiation Detection in Saline Environment
Chapter7 4 7. Optimization of Cosmic Radiation Detection in Saline Environment
Chapter7 3 7. Optimization of Cosmic Radiation Detection in Saline Environment
Chapter7 2 7. Optimization of Cosmic Radiation Detection in Saline Environment
Chapter7 1 7. Optimization of Cosmic Radiation Detection in Saline Environment
Chapter6 2 6. Calculation of the Dose for Public Individuals Due to a Severe Accident at the Angra 2 Nuclear Plant, Brazil