Interim Status Report on Lead-Cooled Fast Reactor (Lfr) Research and Development. Page: 4 of 36
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Table of Contents
Abstract iv
1. Argonne National Laboratory 1
1.1. Introduction 1
1.2. Burnup Simulations 2
1.3. Reactivity Coefficients 8
1.4. Control Rod Worth Requirements and Control Rod Reactivity 10
1.5. Summary of Core Concept Development Analyses 12
1.6. References 13
2. Lawrence Livermore National Laboratory 14
2.1. International Interactions 14
2.2. ODS Steels in Corrosive Lead-Bismuth Eutectic 15
2.2.1. LBE-Cooled Fast Reactor Hot Spot Simulation: Low-Cr
ODS Steels 15
2.2.2. Improved Corrosion Resistance in Al-Diffusion Treated
F/M Steels 16
2.2.3. Low-Cr ODS and F/M Steels with Modified Surface
Structure 17
2.2.4. Corrosion Resistant High-Cr ODS Ferritic Steels 18
2.3. References 20
3. Los Alamos National Laboratory 21
3.1. Introduction 21
3.2. Published or Submitted Papers 21
3.3. DELTA PbO Experiment 24
3.4. Effects of Oxides on Steels and Oxygen in LBE on Heat Transfer 24
3.5. Long-Term Oxidation/Corrosion Performance of Candidate Steels in
LBE and Pb 25
4. Acknowledgements 27
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Tzanos, C. P.; Sienicki, J. J.; Moisseytsev, A.; Smith, C. F.; de Caro, M.; Halsey, W. G. et al. Interim Status Report on Lead-Cooled Fast Reactor (Lfr) Research and Development., report, March 31, 2008; United States. (https://digital.library.unt.edu/ark:/67531/metadc901583/m1/4/: accessed April 19, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.