Open AccessCanister Transfer Facility Criticality Calculations
Author(s) -
J.E. Monroe-Rammsy
Publication year - 2000
Language(s) - English
Resource type - Reports
DOI - 10.2172/893821
Subject(s) - criticality , mox fuel , radioactive waste , nuclear engineering , environmental science , triga , spent nuclear fuel , scope (computer science) , waste management , engineering , nuclear physics , physics , computer science , research reactor , plutonium , neutron , programming language
The objective of this calculation is to evaluate the criticality risk in the surface facility for design basis events (DBE) involving Department of Energy (DOE) Spent Nuclear Fuel (SNF) standardized canisters (Civilian Radioactive Waste Management System [CRWMS] Management and Operating Contractor [M&O] 2000a). Since some of the canisters will be stored in the surface facility before they are loaded in the waste package (WP), this calculation supports the demonstration of concept viability related to the Surface Facility environment. The scope of this calculation is limited to the consideration of three DOE SNF fuels, specifically Enrico Fermi SNF, Training Research Isotope General Atomic (TRIGA) SNF, and Mixed Oxide (MOX) Fast Flux Test Facility (FFTF) SNF