Repository logo
Log in(current)
Repository logoMIT Open ScholarshipDSpace@MIT
  1. Home
  2. MIT Libraries
  3. MIT Theses
  4. Graduate Theses
  5. A model for the evolution of gas pressure and composition during sealed storage of metallic uranium fuel

A model for the evolution of gas pressure and composition during sealed storage of metallic uranium fuel

Thumbnail Image
Download
Name

42138270-MIT.pdf

Description
Full printable version
Size

6.18 MB

Format

Adobe PDF

Checksum (MD5)

ccfa3339fb391880fbc6d13369ad78bd

Author(s)
Shell, Lisa Stiles
Advisor(s)
R.G. Ballinger and R.M. Latanison.
Date Issued
1997
Publisher
Massachusetts Institute of Technology
Abstract
A model has been developed to predict the pressure generation and concentrations of oxygen and hydrogen gas in a Multi-Canister Overpack (MCO) containing metallic uranium N Reactor fuel during staging, drying, conditioning, and storage at the Hanford Site. Ass0ciated uncertainties with each parameter were also calculated. The mechanisms that were included in the analysis were: -- Uranium Corrosion in which oxygen is consumed, or water is consumed and hydrogen is produced, -- Uranium Hydriding in which hydrogen is consumed, and -- Radiolysis in which water is consumed and hydrogen and oxygen are produced. The model characterizes the evolution of gases inside the MCO for the three ,egimes in which the fuel will be staged or stored. Prior to treatment the fuel will be immersed in water in the MCO. Proceeding the first treatment step, the MCO will contain no free water, but water vapor will contribute to a moist atmosphere. After the last treatment step, the inside of the MCO will be dry with only tightly-bound chemisorbed water remaining associated with sludge that will be present with the fuel. The model shows that for likely conditions inside the MCO, the container will not pressurize during its expected service life. The model also shows the effects that varying parameters have on the final pressure.
Description
Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1997.
Includes bibliographical references (leaves 52-54).
Subjects
Nuclear Engineering
MIT Department
Massachusetts Institute of Technology. Department of Nuclear Science and Engineering
Terms of Use
M.I.T. theses are protected by copyright. They may be viewed from this source for any purpose, but reproduction or distribution in any format is prohibited without written permission. See provided URL for inquiries about permission.
http://dspace.mit.edu/handle/1721.1/7582
Persistent DSpace Link
http://hdl.handle.net/1721.1/9589
Repository logo
PrivacyPermissionsAccessibilityContact us
Repository logo
Notify us about copyright concerns.