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EQ6 Calculations for Chemical Degradation of PWR LEU and PWR MOX Spent Fuel Waste Packages

EQ6 Calculations for Chemical Degradation of PWR LEU and PWR MOX Spent Fuel Waste Packages

Author(s)
Paul L. Cloke
Publication Date
The Monitored Geologic Repository (MGR) Waste Package Operations of the Civilian Radioactive Waste Management System Management & Operating (CRWMS M&O) contractor performed calculations to provide input to the design of a waste package (WP). This document analyzes the degradation processes of two types of pressurized water reactor (PWR) spent nuclear fuel (SNF): • Fuel fabricated from low enriched uranium oxide, which has been used, or will ~ used, in commercial nuclear power plants.
criticality low-enriched uranium monitored geologic repository storage mox fuel waste package degradation pwr snf corrosion plutonium oxide geochemical analysis bba000000-01717-0210-00009 uranium oxide

EBS Radionuclide Transport Abstraction

EBS Radionuclide Transport Abstraction

Author(s)
Sandia National Laboratories
Publication Date

The purpose of this report is to develop and analyze the Engineered Barrier System (EBS) Radionuclide Transport Abstraction Model, consistent with Level I and Level II model validation, as identified in Technical Work Plan for: Near-Field Environment: Engineered Barrier System: Radionuclide Transport Abstraction Model Report (BSC 2006 [DIRS 177739]). The EBS Radionuclide Transport Abstraction (or RTA) is the conceptual model used in the Total System Performance Assessment (TSPA) to determine the rate of radionuclide releases from the EBS to the unsaturated zone (UZ).

yucca mountain total system performance assessment igneous intrusion waste package degradation corrosion radionuclide transport seepage drip shield engineered barrier system unsaturated zone

Extended Storage and Transportation - Evaluation of Drying Adequacy

Extended Storage and Transportation - Evaluation of Drying Adequacy

Author(s)
CNWRA ,
Hundal Jung ,
Pavan Shukla ,
Tae Ahn ,
Lynn Tipton ,
Kaushik Das ,
Xihua He ,
Debashis Basu
Publication Date

The U.S. Nuclear Regulatory Commission (NRC) is evaluating the safety and security of spent nuclear fuel (SNF) stored in dry casks for extended time periods before transportation to a location where the SNF is further processed or permanently disposed.

criticality storage vacuum drying spent fuel degradation corrosion ml13169a039 residual water
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