Author: J. O. BarnerPublisher:
ISBN:
Category : Nuclear fuel claddings
Languages : en
Pages : 124
Book Description
Electrically Heated Ex-reactor Pellet-cladding Interaction (PCI) Simulations Utilizing Irradiated Zircaloy Cladding
Author: J. O. BarnerPublisher:
ISBN:
Category : Nuclear fuel claddings
Languages : en
Pages : 124
Book Description
Electrically Heated Ex-reactor Pellet-cladding Interaction (PCI) Simulations Utilizing Irradiated Zircaloy Cladding. [PWR].
![Electrically Heated Ex-reactor Pellet-cladding Interaction (PCI) Simulations Utilizing Irradiated Zircaloy Cladding. [PWR]. PDF](https://books.google.com/books/content/images/frontcover/1X9knQAACAAJ?fife=w80-h100)
Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
In a program sponsored by the Fuel Systems Research Branch of the US Nuclear Regulatory Commission, a series of six electrically heated fuel rod simulation tests were conducted at Pacific Northwest Laboratory. The primary objective of these tests was to determine the susceptibility of irradiated pressurized-water reactor (PWR) Zircaloy-4 cladding to failures caused by pellet-cladding mechanical interaction (PCMI). A secondary objective was to acquire kinetic data (e.g., ridge growth or relaxation rates) that might be helpful in the interpretation of in-reactor performance results and/or the modeling of PCMI. No cladding failures attributable to PCMI occurred during the six tests. This report describes the testing methods, testing apparatus, fuel rod diametral strain-measuring device, and test matrix. Test results are presented and discussed.
Energy Research Abstracts
Author: Experimental Support and Development of Single-rod Fuel Codes Program
Author: D. D. LanningPublisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 64
Book Description
Government Reports Announcements & Index
Author: Government Reports Annual Index
Author: Publisher:
ISBN:
Category : Government reports announcements & index
Languages : en
Pages : 878
Book Description
Title List of Documents Made Publicly Available
Author: Publisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages : 936
Book Description
Fracture Behavior of Zircaloy Spent-fuel Cladding
Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
The Zircaloy cladding of water reactor fuel rods is susceptible to local breach-type failure, commonly known as pellet-cladding interaction (PCI) failure, during operational and off-normal power transients after the fuel has achieved a sufficiently high burnup. An optimization of power ramp procedures or fuel rod fabrication to minimize the cladding failure would result in a significant decrease in radiation exposure of plant personnel due to background and airborne radioactivity as well as an extension of core life in terms of allowable off-gas radioactivity. As part of a program to provide a better understanding of the fuel rod faiure phenomenon and to facilitate the formulation of a better failure criterion, a mechanistic study of the deformation and fracture behavior of high-burnup spent-fuel cladding is in progress under simulated PCI conditions.
INIS Atomindex
Author: Government Reports Annual Index: Keyword A-L
Author: Publisher:
ISBN:
Category : Government reports announcements & index
Languages : en
Pages : 976
Book Description