frapcon analysis of cladding performance during dry storage operations

Clicks: 191
ID: 203761
2018
Free PDF
Article Quality & Performance Metrics
Overall Quality
Not rated
Combines reader engagement with the AI quality analysis. This article has not been analysed, so there is no overall score — reader engagement is measured and shown alongside.
AI Quality Assessment
Not analyzed
Readership in this journal
Steady

Ranked #274 of 357 articles by views in Journal of hazardous materials

Most read Least read

Bar heights use a square-root scale. Only the 120 most-read articles are drawn; the journal has 357 in total.

Mint this article as an NFT
Not yet minted

Create a permanent, verifiable on-chain record of this article on the Scimatic Network. The NFT is held in your Journament account, and you can withdraw it to your own wallet at any time.

5 SUSD one-off · no wallet required
Sign in to mint
Abstract
There is an increasing need in the United States and around the world to move used nuclear fuel from wet storage in fuel pools to dry storage in casks stored at independent spent fuel storage installations or interim storage sites. Under normal conditions, the Nuclear Regulatory Commission limits cladding temperature to 400°C for high-burnup (>45 GWd/mtU) fuel, with higher temperatures allowed for low-burnup fuel. An analysis was conducted with FRAPCON-4.0 on three modern fuel designs with three representative used nuclear fuel storage temperature profiles that peaked at 400°C. Results were representative of the majority of US light water reactor fuel. They conservatively showed that hoop stress remains below 90 MPa at the licensing temperature limit. Results also show that the limiting case for hoop stress may not be at the highest rod internal pressure in all cases but will be related to the axial temperature and oxidation profiles of the rods at the end of life and in storage. Keywords: Dry Storage, FRAPCON, Fuel Performance, Radial Hydride Reorientation, Vacuum Drying
Reference Key
richmond2018nuclearfrapcon Use this key to autocite in the manuscript while using SciMatic Manuscript Manager or Thesis Manager
Authors ;David J. Richmond;Kenneth J. Geelhood
Journal Journal of hazardous materials
Year 2018
DOI
DOI not found
URL
http://www.sciencedirect.com/science/article/pii/S1738573317307477
Keywords
nuclear engineering atomic power

Citations

No citations found. To add a citation, contact the admin at info@scimatic.org

Comments

No comments yet. Be the first to comment on this article.