Published June 1996 | Version v1
Report Open

Surface area considerations for corroding N reactor fuel

Description

The N Reactor fuel is corroding at sites where the Zircaloy cladding was damaged when the fuel was discharged from the reactor. Corroding areas are clearly visible on the fuel stored in open cans in the K East Basin. There is a need to estimate the area of the corroding uranium to analyze aspects of fuel behavior as it is transitioned. from current wet storage to dry storage. In this report, the factors that contribute to open-quotes trueclose quotes surface area are analyzed in terms of what is currently known about the N Reactor fuel. Using observations from a visual examinations of the fuel in the K East wet storage facility, a value for the corroding geometric area is estimated. Based on observations of corroding uranium and surface roughness values for other metals, a surface roughness factor is also estimated and applied to the corroding K East fuel to provide an estimated open-quotes trueclose quotes surface area. While the estimated area may be modified as additional data become available from fuel characterization studies, the estimate provides a basis to assess effects of exposed uranium metal surfaces on fuel behavior in operations involved in transitioning from wet to dry storage, during shipment and staging, conditioning, and dry interim storage

Availability note (English)

MF available from INIS under the Report Number; Also available from OSTI as DE96012331; NTIS; US Govt. Printing Office Dep.

Files

27068825.pdf

Files (1.4 MB)

Name Size Download all
md5:89c91865e42d91f800d1271e3684fc54
1.4 MB Preview Download

Additional details

Publishing Information

Imprint Pagination
53 p.
Report number
PNNL--11174

Optional Information

Contract/Grant/Project number
Contract AC06-76RL01830
Funding organization
USDOE, Washington, DC (United States).