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Title: Screening Analysis of Criticality Features, Events, and Processes for License Application

Technical Report ·
DOI:https://doi.org/10.2172/850434· OSTI ID:850434

This report documents the screening analysis of postclosure criticality features, events, and processes. It addresses the probability of criticality events resulting from degradation processes as well as disruptive events (i.e., seismic, rock fall, and igneous). Probability evaluations are performed utilizing the configuration generator described in "Configuration Generator Model", a component of the methodology from "Disposal Criticality Analysis Methodology Topical Report". The total probability per package of criticality is compared against the regulatory probability criterion for inclusion of events established in 10 CFR 63.114(d) (consider only events that have at least one chance in 10,000 of occurring over 10,000 years). The total probability of criticality accounts for the evaluation of identified potential critical configurations of all baselined commercial and U.S. Department of Energy spent nuclear fuel waste form and waste package combinations, both internal and external to the waste packages. This criticality screening analysis utilizes available information for the 21–Pressurized Water Reactor Absorber Plate, 12–Pressurized Water Reactor Absorber Plate, 44–Boiling Water Reactor Absorber Plate, 24–Boiling Water Reactor Absorber Plate, and the 5-Defense High-Level Radioactive Waste/U.S. Department of Energy Short waste package types. Where defensible, assumptions have been made for the evaluation of the following waste package types in order to perform a complete criticality screening analysis: 21–Pressurized Water Reactor Control Rod, 5–Defense High-Level Radioactive Waste/U.S. Department of Energy Long, and 2–Multi-Canister Overpack/2–Defense High-Level Radioactive Waste package types. The inputs used to establish probabilities for this analysis report are based on information and data generated for the Total System Performance Assessment for the License Application, where available. This analysis report determines whether criticality is to be included or excluded from the Total System Performance Assessment for the License Application. The updated criticality features, events, and processes screening analysis contained herein are prepared in accordance with the guidance specified in "The Development of the Total System Performance Assessment-License Application Features, Events, and Processes".

Research Organization:
Yucca Mountain Project, Las Vegas, NV (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); USDOE Office of Civilian Radioactive Waste Management (RW)
DOE Contract Number:
AC28-01RW12101
OSTI ID:
850434
Report Number(s):
ANL-EBS-NU-000008-Rev.01; DOC.20041022.0001, DC#40661
Country of Publication:
United States
Language:
English