Nuclear criticality safety bounding analysis for the in-tank-precipitation (ITP) process, impacted by fissile isotopic weight fractions
Description
The In-Tank Precipitation process (ITP) receives High Level Waste (HLW) supernatant liquid containing radionuclides in waste processing tank 48H. Sodium tetraphenylborate, NaTPB, and monosodium titanate (MST), NaTi2O5H, are added for removal of radioactive Cs and Sr, respectively. In addition to removal of radio-strontium, MST will also remove plutonium and uranium. The majority of the feed solutions to ITP will come from the dissolution of supernate that had been concentrated by evaporation to a crystallized salt form, commonly referred to as saltcake. The concern for criticality safety arises from the adsorption of U and Pt onto MST. If sufficient mass and optimum conditions are achieved then criticality is credible. The concentration of u and Pt from solution into the smaller volume of precipitate represents a concern for criticality. This report supplements WSRC-TR-93-171, Nuclear Criticality Safety Bounding Analysis For The In-Tank-Precipitation (ITP) Process. Criticality safety in ITP can be analyzed by two bounding conditions: (1) the minimum safe ratio of MST to fissionable material and (2) the maximum fissionable material adsorption capacity of the MST. Calculations have provided the first bounding condition and experimental analysis has established the second. This report combines these conditions with canyon facility data to evaluate the potential for criticality in the ITP process due to the adsorption of the fissionable material from solution. In addition, this report analyzes the potential impact of increased U loading onto MST. Results of this analysis demonstrate a greater safety margin for ITP operations than the previous analysis. This report further demonstrates that the potential for criticality in the ITP process due to adsorption of fissionable material by MST is not credible
Availability note (English)
MF available from INIS under the Report Number; Also available from OSTI as DE94014874; NTIS; US Govt. Printing Office Dep.Files
25073561.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 134 p.
- Report number
- WSRC-TR--94-004
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 25073561
- Subject category
- S42: ENGINEERING; S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- ADSORBENTS; ADSORPTION; BOUNDARY CONDITIONS; COMPILED DATA; CRITICALITY; HIGH-LEVEL RADIOACTIVE WASTES; PLUTONIUM; RADIOACTIVE WASTE FACILITIES; RADIOACTIVE WASTE PROCESSING; SAFETY ANALYSIS; SAVANNAH RIVER PLANT; SORPTIVE PROPERTIES; URANIUM
- Descriptors DEC
- ACTINIDES; DATA; ELEMENTS; INFORMATION; MANAGEMENT; MATERIALS; METALS; NATIONAL ORGANIZATIONS; NUCLEAR FACILITIES; NUMERICAL DATA; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; SORPTION; SURFACE PROPERTIES; TRANSURANIUM ELEMENTS; US AEC; US DOE; US ERDA; US ORGANIZATIONS; WASTE MANAGEMENT; WASTE PROCESSING; WASTES
Optional Information
- Contract/Grant/Project number
- Contract AC09-89SR18035
- Funding organization
- USDOE, Washington, DC (United States).