Open AccessSpent nuclear fuel project operational description
Author(s) -
D.R. Duncan
Publication year - 1996
Language(s) - English
Resource type - Reports
DOI - 10.2172/659211
Subject(s) - depleted uranium , uranium , spent nuclear fuel , plutonium , work (physics) , natural uranium , environmental science , nuclear engineering , forensic engineering , engineering , waste management , mechanical engineering , chemistry , materials science , nuclear chemistry , metallurgy
This Operational Description is prepared as input to the Multi- Canister Overpack (MCO) Pressurization Analysis. The MCO Pressurization analysis will include topical studies and analyses on fuel/moisture/has behavior areas, modeling of temperature and pressure, and a culminating integrated gas generation and pressurization analysis providing the expected MCO pressure history for normal operating scenarios and for off-normal events. A basis for the temperature and pressure modeling will be this operational description. Its objective is to provide time,temperature, and MCO material loading envelopes for the modeling efforts, both for normal and off-normal events