2 edition of Irradiation history and final postirradiation data for IFA-432 found in the catalog.
Irradiation history and final postirradiation data for IFA-432
D. D. Lanning
by Division of Reactor System Safety, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission in Washington, DC
Written in English
|Statement||prepared by D.D. Lanning.|
|Contributions||U.S. Nuclear Regulatory Commission. Division of Reactor System Safety., Pacific Northwest Laboratory.|
|The Physical Object|
|Pagination||1 v. (various pagings) :|
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Essay topics #2
The irradiation history and final postirradiation examination (PIE) results are presented for the Halden fuel assembly IFA In particular, the three instrumented rods (Rods 2, 3, and 5) that continued to the highest burnup (46 MWd/kgM) are emphasized.
The long survival rate of. Get this from a library. Irradiation history and final postirradiation data for IFA [D D Lanning; U.S. Nuclear Regulatory Commission. Division of. The instrumented six-rod test assembly IFA, sponsored by USNRC, operated in the Halden Reactor from December to Maywith surviving fuel thermocouples, neutron detectors and pressure transducers.
Peak burnups of 46 MWd/kgM were achieved. Interim destructive examination data were. Sponsor a Book. Nuclear fuel rods 17 works Search for books with subject Nuclear fuel rods.
Irradiation history and final postirradiation data for IFA D. Lanning Data base on the behavior of high burnup fuel rods with Zr-1% Nb cladd L. Yegorova Read. Available in the National Library of Australia collection. Author: Y Lan; Format: Book; p.: ill. ; 22 cm.
The book presented is designed to function both as a text for first-year graduate courses in nuclear materials and as a reference for workers involved. Search the history of over billion web pages on the Internet. search Search the Wayback Machine.
Featured texts All Books All Texts latest This Just In Smithsonian Libraries FEDLINK (US) Genealogy Lincoln Collection Full text of "Monthly catalog. PNNL Rev. 2 Material Property Correlations: Comparisons between FRAPCON, FRAPTRAN, and MATPRO September WG Luscher KJ Geelhood IE Porter.
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An integral assessment has been performed for the U.S. Nuclear Regulatory Commission by Pacific Northwest National Laboratory to quantify the predictive capabilities of FRAPCON-3, a steady-state fuel behavior code designed to analyze fuel behavior from beginning-of-life to burnup levels of 65 GWd/MTU.
5 Data of Maki 5 "3- from two samples oxidized in steam are reproduced in Table The data cover a small temperature range and show a sharp increase in conductivity between and K. The principal. NUREG/CRRev. 2, Vol 4 Zircaloy Oxides. recommendation for the data is that they were taken with black oxide from zircaloy tubes.
Comparisons are also made with MATPRO, which is a compilation of material property correlations with an extensive history of use with various fuel performance and severe accident codes. In addition to model-to-model comparisons, model-to-data comparisons and source codes for the FRAPCON and FRAPTRAN correlations are provided.