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                                                                     Order 
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                                                                     Paper Title 
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                                                              1  | 
                                                              Experimental Comparison between High Purity Germanium and Scintillator Detectors for Determining Burnup, Cooling Time and Decay Heat of Used Nuclear Fuel - 14488  
Peter Jansson, Uppsala University (Sweden); Sophie Grape, Uppsala University (Sweden); Henrik Liljenfeldt, Swedish Nuclear Fuel and Waste Management Company (SKB AB) (Sweden); Stephen J. Tobin, Los Alamos National Laboratory (USA)   | 
                                                             
                                                            
                                                            
                                                              2  | 
                                                              Solubility Validation from Boildown Data for Hanford Tank Liquids - 14445  
Stephen Agnew, Columbia Energy & Environmental (USA); Robert Wilson, Columbia Energy & Environmental (USA); Gene Ramsey, Washington River Protection Solutions (USA)   | 
                                                             
                                                            
                                                            
                                                              3  | 
                                                              Binary Pitzer Model Parameters for Predicting the Solubility of Key Electrolytes in Hanford Waste - 14215  Jacob Reynolds, Washington River Protection Solutions (USA); Robert Carter, Washington River Protection Solutions (USA); 
Kayla Pierson, Washington River Protection Solutions (USA)   | 
                                                             
                                                            
                                                            
                                                              4  | 
                                                              Characterization of Uranium Residue from Solid Mo-99 Manufacturing Waste and Development of a Recovery Process using Carbonate Solution - 14399  
Lize Stassen, Necsa (South Africa); Janine Suthiram, Necsa (South Africa); James Topkin, Necsa (South Africa)   | 
                                                             
                                                            
                                                            
                                                              5  | 
                                                              Transition of Oil and Gas Dynamic Simulation to Nuclear Applications Delivers Big Rewards - 14466  
David Cuming, DBD Limited (United Kingdom)   | 
                                                             
                                                            
                                                            
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