Estimation of alkali metal mole percent and weight of calcined solids for ICPP calcine

O`Brien, B.H.

doi:10.2172/124973

Cited by 8 publications

(12 citation statements)

References 0 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…The HPM adds the amount of oxygen required for a charge balance with the other species in the calcine. O 'Brien (1995) provides further details on this calculation method and the compounds assumed to form in the calcine.…”

Section: Calcine Composition Calculation Methodsmentioning

confidence: 99%

Calcined Waste Storage at the Idaho Nuclear Technology and Engineering Center

Staiger¹,

Swenson²

2007

View full text Add to dashboard Cite

show abstract

Section: Calcine Composition Calculation Methodsmentioning

confidence: 99%

Calcined Waste Storage at the Idaho Nuclear Technology and Engineering Center

Staiger¹,

Swenson²

2007

View full text Add to dashboard Cite

show abstract

“…For most of the calcination history (all of WCF operation and the 500 o C NWCF operation), the HPM assumed a fixed mole fraction (0.66) of the alkali metals sodium and potassium form nitrates, and the remaining fraction (0.34) formed oxides (O'Brien 1995). In 1999 and 2000, a new "high-temperature" calcination flowsheet was successfully tested.…”

Section: Historical Processing Model Calcine Composition Estimatementioning

confidence: 99%

Addendum to the Calcined Waste Storage at the Idaho Nuclear Technology Center

Staiger¹,

Swenson²,

Thomas³

2004

View full text Add to dashboard Cite

This report is an addendum to the report Calcined Waste Storage at the Idaho Nuclear Technology and Engineering Center, INEEL/EXT-98-00455 Rev. 1, June 2003. The original report provided a summary description of the Calcined Solids Storage Facilities (CSSFs). It also contained dozens of pages of detailed data tables documenting the volume and composition (chemical content and radionuclide activity) of the calcine stored in the CSSFs and the liquid waste from which the calcine was derived. This addendum report compiles the calcine composition data from the original report. It presents the compiled data in a graphical format with units (weight percent, curies per cubic meter, and nanocuries per gram) that are commonly used in regulatory and waste acceptance criteria documents. The compiled data are easier to use and understand when comparing the composition of the calcine with potential regulatory or waste acceptance criteria.This addendum report also provides detailed explanations for the large variability in the calcine composition among the CSSFs. The calcine composition varies as a result of reprocessing different types of fuel that had different cladding materials. Different chemicals were used to dissolve the various types of fuel, extract the uranium, and calcine the resulting waste. This resulted in calcine with variable compositions. This addendum report also identifies a few trace chemicals and radionuclides for which the accuracy of the amounts estimated to be in the calcine could be improved by making adjustments to the assumptions and methods used in making the estimates.A compact disk of this report is included to facilitate data manipulation and analysis. iv v SUMMARYThis report provides data on the chemical content and radionuclide activity of the calcine currently stored at the Idaho Nuclear Technology and Engineering Center (INTEC). Calcine composition data will be required for the future retrieval, treatment, and disposal of the calcine. There are few historical calcine samples that provide analytical calcine composition data. Obtaining additional calcine samples will be difficult because the calcine storage facilities were not specifically designed for calcine sampling. A previous report, Calcined Waste Storage at the Idaho Nuclear Technology and Engineering Center INEEL/EXT-98-00455 Rev 1, estimated the calcine composition based upon extensive historical process data. These data include sample analyses of the liquid waste from which the calcine was formed, Calciner operating history, Calcine Solids Storage Facility (CSSF) operating history, and knowledge of the INTEC fuel reprocessing and calcination processes.This report compiles and analyzes the calcine composition data given in INEEL/EXT-98-00455 Rev 1. This report provides the chemical content of the calcine on a weight percentage basis and the radionuclides on an activity-per-unit-mass (nCi/g) or activity-per-unit-volume (Ci/m 3 ) basis. These composition bases are commonly used in national standards and regulations related to was...

show abstract

“…Keep in mind these results are only an estimate. Calcination is not an equilibrium process and the rates of compound formation are unknown 8 . Although a mean bed temperature is assumed, bed material undergoes a cyclic sequence of cooling and heating during its migration in the fluidized bed circulation pattern; where this cycle starts is arbitrary.…”

Section: Analytementioning

confidence: 99%

Dissolution Kinetics of Alumina Calcine

Batcheller¹

2001

View full text Add to dashboard Cite

SUMMARYDissolution kinetics of alumina type non-radioactive calcine was investigated as part of ongoing research that addresses permanent disposal of Idaho High Level Waste (HLW). Calcine waste was produced from the processing of nuclear fuel at the Idaho Nuclear Technology and Engineering Center (INTEC). Acidic radioactive raffinates were solidified at ~500ºC in a fluidized bed reactor to form the dry granular calcine material. Several Waste Management alternatives for the calcine are presented in the Idaho High Level Waste Draft EIS. The Separations Alternative addresses the processing of the calcine so that the HLW is ready for removal to a national geological repository by the year 2035. Calcine dissolution is the key front-end unit operation for the separations alternative.Because aluminum and zirconium-type fuels were predominately reprocessed at the INTEC, alumina and zirconia-type calcines were produced and stored. Dissolution kinetics testing with non-radioactive pilot plant zirconia calcine has been previously investigated. Similar to that work, the scope of this present alumina calcine dissolution work included: 1) chemical and physical analyses of the calcine material, 2) baseline dissolution testing to determine: order of reaction, activation energy (Arrhenius analysis), and dissolution rate controlling mechanism (chemical reaction or mass transfer limited). Testing was also performed to determine if complete dissolution is equilibrium/solubility inhibited.Chemical and physical analyses were performed on the RSH-1 alumina type pilot plant calcine bed material. Elemental fusion analysis results agree well with microprobe analysis results. An average value of the calcine acid consumption coefficient, b, was determined for RSH-1 bed product material; b = 19.8 grams RSH-1 dissolved per mol of acid consumed. The order of reaction testing revealed that, just as in the case for the Run74 zirconia pilot plant calcine testing, the homogeneous rate form fit the rate data better than the heterogeneous rate form. A characteristic dissolution fractal dimension, D R , was determined for alumina and zirconia pilot plant calcine milled material and bed particles. The result from this fractal treatment of the dissolution data further supports the indication that calcine dissolution is more dependent upon its physical characteristics, rather than its chemical characteristics. Arrhenius testing yielded an apparent activation energy (E A ) of 26.9 kcal/mol for RSH-1 alumina pilot plant calcine under conditions of constant 6 M acid concentration. The dissolution rate controlling mechanism testing results were inconclusive. Nevertheless, it was noted that, just as with all previous calcine dissolution testing, this testing with RSH-1 showed the familiar initial rapid dissolution then the leveling-out of the rate, and the non-attainment of 100% dissolution after long dissolution times-it too had the characteristics of internal mass diffusion controlled dissolution. The equilibrium/solubility inhibition testing results ind...

show abstract

Estimation of alkali metal mole percent and weight of calcined solids for ICPP calcine

Abstract: Portions of this document may be illegible electronic image products. Images are produced from the best available original document.

Cited by 8 publications

References 0 publications

Calcined Waste Storage at the Idaho Nuclear Technology and Engineering Center

Calcined Waste Storage at the Idaho Nuclear Technology and Engineering Center

Addendum to the Calcined Waste Storage at the Idaho Nuclear Technology Center

Dissolution Kinetics of Alumina Calcine

Contact Info

Product

Resources

About