Category of Content

Siting Experience Documents Only

Publication Date

Country

Keywords

Displaying 26 - 50 of 80

slides - CFD Best Practice Guidelines (NUREG-2152), Thermal Modeling Issues, and Generic Communications Related to Vacuum Drying Operations

slides - CFD Best Practice Guidelines (NUREG-2152), Thermal Modeling Issues, and Generic Communications Related to Vacuum Drying Operations

Author(s)
Solis, J.
Publication Date

Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013

slides nei used fuel management meeting cfd thermal modeling vacuum drying

Evaluation of Internal Criticality of the Plutonium Disposition MOX SNF Waste Form

Evaluation of Internal Criticality of the Plutonium Disposition MOX SNF Waste Form

Author(s)
OCRWM
Publication Date

The purpose of this calculation is to perform a parametric study to determine the effects of fission product leaching, assembly collapse, and iron oxide loss on the reactivity of a waste package containing mixed oxide spent nuclear fuel. Previous calculations (CRWMS M&O 1998a) have shown that the criticality control features of the waste package are adequate to prevent criticality of a flooded WP for all the enrichment/burnup pairs expected for the MOX SNF.

spent fuel fission products criticality analysis plutonium mcnp mox fuel used fuel

Validation of important fission product evaluations through CERES integral benchmarks

Validation of important fission product evaluations through CERES integral benchmarks

Author(s)
Dean, C. J. ,
Smith, P. J. ,
Perry, R. J.
Publication Date

Optimization of energy resources suggests increased fuel residence in reactor cores and hence improved
fission product evaluations are required. For thermal reactors the fission product cross sections in the JEF2.2 and
JEFF3.1 libraries plus new evaluations from WPEC23 are assessed through modelling the CERES experiment in
the DIMPLE reactor. The analysis uses the lattice code WIMS10. Cross sections for 12 nuclides are assessed. The
thermal cross section and low energy resonance data for 147,152Sm and 155Gd are accurate to within 4%. Similar data

fission products criticality analysis doi: 10.1051/ndata:07172 nuclear data ceres

Evaluation of Cross-Section Sensitivities in Computing Burnup Credit Fission Product Concentrations

Evaluation of Cross-Section Sensitivities in Computing Burnup Credit Fission Product Concentrations

Author(s)
Gauld, I. C. ,
Mueller, D. E.
Publication Date

U.S. Nuclear Regulatory Commission Interim Staff Guidance 8 (ISG-8) for burnup credit covers actinides only, a position based primarily on the lack of definitive critical experiments and adequate radiochemical assay data that can be used to quantify the uncertainty associated with fission product credit.

burnup credit fission products criticality analysis ornl/tm-2005/48 nuclear data

slides - Industry Response to NRC's Request for Comments on Retrievability, Cladding Integrity and 10 CFR 71/72 Alignment

slides - Industry Response to NRC's Request for Comments on Retrievability, Cladding Integrity and 10 CFR 71/72 Alignment

Author(s)
Levin, A. H.
Publication Date

Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013

nrc slides retrievability nei used fuel management meeting cladding integrity industry response 10 cfr 71 10 cfr 72
Disclaimer: Note that this page contains links to external sites. When leaving the CURIE site, please note that the U.S. Department of Energy and Pacific Northwest National Laboratory do not control or endorse the content or ads on these sites.
Sponsored by: