University of Illinois Urbana-Champaign

Evaluation of off normal temperature events in stored nuclear fuel cladding on storage limits utilizing a modified dating code

Kriz, Zachary Daniel

Content Files
KRIZ-THESIS-2015.pdf

Permalink

https://hdl.handle.net/2142/78536

Description

Title
Evaluation of off normal temperature events in stored nuclear fuel cladding on storage limits utilizing a modified dating code
Author(s)
Kriz, Zachary Daniel
Issue Date
2015-04-29
Department of Study
Nuclear, Plasma, & Rad Engr
Discipline
Nuclear, Plasma, Radiolgc Engr
Degree Granting Institution
University of Illinois at Urbana-Champaign
Degree Name
M.S.
Degree Level
Thesis
Date of Ingest
2015-07-22T22:18:02Z
Keyword(s)
  • Zircaloy
  • cladding
  • storage limits
Abstract
The purpose of this study was to utilize a modified DATING code to evaluate the effects off normal temperature conditions occurring during dry storage would have on allowable storage limits for Zircaloy cladding. Towards this, Zircaloy creep tubes were used to perform creep studies in a temperature range of 300-500⁰C with an applied stress range of 40-65 MPa. This allowed for the development of updated creep rate equations with the forms utilized in past studies by Mayuzumi and Matsuo to be fit. These fit equations along with the original mechanistic creep equations from the DATING code were used to evaluate the effects of off normal temperature events ranging from 10-100⁰C beginning at points in the fuels lifetime ranging from 5%-75% of the expected life time of 40 years. The results of this evaluation were that while differing allowable limits are found using the original rate equations and the equations fit to this studies data both cases show no noticeable effect on the allowable limit.
Graduation Semester
2015-5
Type of Resource
text
Permalink
http://hdl.handle.net/2142/78536
Copyright and License Information
Copyright 2015 Zachary Kriz

Owning Collections

Graduate Dissertations and Theses at Illinois PRIMARY
Graduate Theses and Dissertations at Illinois
Dissertations and Theses - Nuclear, Plasma, and Radiological Engineering