Determination of Reportable Radionuclides for DWPF Sludge Batch 5 (Macrobatch 6)

Abstract

Pm-147 Method 8 3.4 Calculated Activities of the Remaining Radionuclides 9 3.4.1 Nb-93m 3.4.2 Pd-107 9 3.4.3 Cd-113m 3.4.4 Cs-135 11 4.0 RESULTS AND DISCUSSION 4.1 Sample Solids and Densities 12 4.2 Summary of the Activities and Radionuclides for Input 4.3 Identification of Reportable Radionuclides 14 4.4 The Ratio by Weight of U and Pu Isotopes 5.0 CONCLUSIONS 6.0 RECOMMENDATIONS 19 7.0 REFERENCES 20 8.0 ACKNOWLEDGEMENTS 22 APPENDIX A. Activities of Dried Sludge in Year 2015 (μCi/g) APPENDIX B. Activities of Dried Sludge in Year 2115 (μCi/g) APPENDIX C. Activities of Dried Sludge in Year 2215 (μCi/g) APPENDIX D. Activities of Dried Sludge in Year 2315 (μCi/g) APPENDIX E. Activities of Dried Sludge in Year 2415 (μCi/g) 31 APPENDIX F. Activities of Dried Sludge in Year 2515 (μCi/g) 33 APPENDIX G. Activities of Dried Sludge in Year 2615 (μCi/g) SRNL-STI-2009-00821 Revision 0 iv APPENDIX H. Activities of Dried Sludge in Year 2715 (μCi/g) 37 APPENDIX I. Activities of Dried Sludge in Year 2815 (μCi/g) 39 APPENDIX J. Activities of Dried Sludge in Year 2915 (μCi/g) 41 APPENDIX K. Activities of Dried Sludge in Year 3015 (μCi/g) 43 APPENDIX L. Activities of Dried Sludge in Year 3115 (μCi/g) Revision 0 1

Analysis of Sludge Batch 4 (Macrobatch 5) for Canister S02902 and Sludge Batch 5 (Macrobatch 6) for Canister S03317 DWPF Pour Stream Glass Samples

“…16 The SDF will be used in Section 3.3 to calculate the concentration of radionuclides that were not directly measured in the glass. 2 However, in an amendment to the Technical Task Request (TTR), five additional radionuclides in SB5 were requested to be analyzed for DWPF facility radiological engineering purposes, 18 resulting in a total of thirty-three reportable radionuclides for SB5. Table 3-7 and Table 3-8 list the radionuclide content in the SB4 and SB5 pour stream glasses, respectively.…”

Potential Application Of Radionuclide Scaling Factors To High Level Waste Characterization

“…5 In cases where an alternate reference was utilized, the reference was specifically cited. The relative radionuclide solubilities and distributions were taken from a series of references: reports addressing characterization of DWPF sludge batches, [6][7][8][9][10][11][12][13] reports addressing characterization of Tank Farm saltcake and supernatant, [14][15][16] and miscellaneous reports focusing on concentrations and distributions of specific radionuclides. [17][18][19] Since the primary sources of fission products in SRS waste are from fission of U-235 used to generate neutrons and fission of U-235 in uranium irradiated to generate Pu-239, all of the fission yields identified in this report are those applicable to U-235, as opposed to those applicable to U-233 or Pu-239.…”

Determination Of Reportable Radionuclides For DWPF Sludge Batch 7B (Macrobatch 9)

“…For previous sludge batches both the Zr-93 and Nb-93m became reportable after the waste was ~100 years old. 21,22,23,24,25,26,7 The concentration of Nb-93m during SB7b vitrification can be calculated if the age of the sludge and the concentration of Zr-93 are known.…”

“…Sn-121m became reportable only in the year 2215. Previous transient reportability has been cited for Am-242m 23,24,25,26 and for Cf-249 26 . The data for these intermediate year calculations can be found in Appendices B-K.…”