Commercial Spent Nuclear Fuel Waste Package Misload Analysis

Technical Report · Tue Jul 26 00:00:00 EDT 2005

DOI:https://doi.org/10.2172/899940· OSTI ID:899940

Alsaed, Abdelhalim ^[1]

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1. Yucca Mountain Project, Las Vegas, NV (United States)

The purpose of this calculation is to estimate the probability of misloading a commercial spent nuclear fuel waste package with a fuel assembly(s) that has a reactivity (i.e., enrichment and/or burnup) outside the waste package design. The waste package designs are based on the expected commercial spent nuclear fuel assemblies and previous analyses. For this calculation, a misloaded waste package is defined as a waste package that has a fuel assembly(s) loaded into it with an enrichment and/or burnup outside the waste package design. An example of this type of misload is a fuel assembly designated for the 21-PWR Control Rod waste package being incorrectly loaded into a 21-PWR Absorber Plate waste package. This constitutes a misloaded 21-PWR Absorber Plate waste package, because the reactivity (i.e., enrichment and/or burnup) of a 21-PWR Control Rod waste package fuel assembly is outside the design of a 21-PWR Absorber Plate waste package. These types of misloads (i.e., fuel assembly with enrichment and/or burnup outside waste package design) are the only types that are evaluated in this calculation. This calculation utilizes information from ''Frequency of SNF Misload for Uncanistered Fuel Waste Package'' (CRWMS M&O 1998) as the starting point. The scope of this calculation is limited to the information available. The information is based on the whole population of fuel assemblies and the whole population of waste packages, because there is no information about the arrival of the waste stream at this time. The scope of this calculation deviates from that specified in ''Technical Work Plan for: Risk and Criticality Department'' in that only waste package misload is evaluated. The remaining issues identified (i.e., flooding and geometry reconfiguration) will be addressed elsewhere. The intended use of the calculation is to provide information and inputs to the Preclosure Safety Analysis Department. Before using the results of this calculation, the reader is cautioned to verify that the assumptions made in this calculation regarding the waste stream, the loading process, and the staging of the spent nuclear fuel assemblies are applicable.

• Research Organization: Yucca Mountain Project, Las Vegas, NV (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• OSTI ID: 899940
• Report Number(s): CAL-WHS-MD-000003-Rev-00A-ECN-01; DOC.20050728.0004, DC# 45175; TRN: US0702326
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
BURNUP
CONTROL ELEMENTS
CRITICALITY
DESIGN
FUEL ASSEMBLIES
GEOMETRY
NUCLEAR FUELS
PLATES
PROBABILITY
SAFETY ANALYSIS
WASTES
Nuclear Criticality Safety Program (NCSP)
Criticality
Risk
Work Plan
Design
Fuel Assemblies
SNF
Spent Nuclear Fuel
Safety Analysis
Control
Waste Package
Absorber