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Title: Slag recycling of irradiated vanadium

Abstract

An experimental inductoslag apparatus to recycle irradiated vanadium was fabricated and tested. An experimental electroslag apparatus was also used to test possible slags. The testing was carried out with slag materials that were fabricated along with impurity bearing vanadium samples. Results obtained include computer simulated thermochemical calculations and experimentally determined removal efficiencies of the transmutation impurities. Analyses of the samples before and after testing were carried out to determine if the slag did indeed remove the transmutation impurities from the irradiated vanadium.

Authors:
 [1]
  1. Carroll College, Helena, MT (United States)
Publication Date:
Research Org.:
EG and G Idaho, Inc., Idaho Falls, ID (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
115735
Report Number(s):
INEL-94/00120
ON: DE96001441; TRN: 95:023329
DOE Contract Number:
AC07-76ID01570
Resource Type:
Thesis/Dissertation
Resource Relation:
Other Information: TH: Thesis; PBD: 5 Apr 1995
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; VANADIUM; RECYCLING; TESTING; SLAGS; TRANSMUTATION; THERMONUCLEAR REACTORS; RADIOACTIVE WASTE PROCESSING; DIAGRAMS

Citation Formats

Gorman, Patrick K. Slag recycling of irradiated vanadium. United States: N. p., 1995. Web. doi:10.2172/115735.
Gorman, Patrick K. Slag recycling of irradiated vanadium. United States. doi:10.2172/115735.
Gorman, Patrick K. Wed . "Slag recycling of irradiated vanadium". United States. doi:10.2172/115735. https://www.osti.gov/servlets/purl/115735.
@article{osti_115735,
title = {Slag recycling of irradiated vanadium},
author = {Gorman, Patrick K.},
abstractNote = {An experimental inductoslag apparatus to recycle irradiated vanadium was fabricated and tested. An experimental electroslag apparatus was also used to test possible slags. The testing was carried out with slag materials that were fabricated along with impurity bearing vanadium samples. Results obtained include computer simulated thermochemical calculations and experimentally determined removal efficiencies of the transmutation impurities. Analyses of the samples before and after testing were carried out to determine if the slag did indeed remove the transmutation impurities from the irradiated vanadium.},
doi = {10.2172/115735},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Wed Apr 05 00:00:00 EDT 1995},
month = {Wed Apr 05 00:00:00 EDT 1995}
}

Thesis/Dissertation:
Other availability
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  • The depth distribution of C, N, and O was measured in the damage layer of a series of heavy-ion irradiated samples of V and V alloyed with C, O, N, Cr, or Ti. Ion-beam analysis using the simultaneously induced nuclear reactions /sup 12/C(d,p/sub o/)/sup 13/C, /sup 16/O(d,p/sub l)/sup 17/O, and /sup 14/N(d,..cap alpha../sub l/)/sup 12/C provided the C, N, and O distributions to a depth of 2 ..mu..m. The profiles were studied as a function of irradiation temperature and displacement dose produced by MeV V or Ar ions. Displacement dose rates of approx.3 x 10/sup -3/ dpa/s provided peak-damage dosesmore » of up to approx.30 dpa, at irradiation temperatures between 250 and 880/sup 0/C. The dominant effect observed was a large enrichment of C, up to approx.20 times the bulk C concentration, in the damage zone of most of the irradiated samples. The C enrichment occurred between approx.400 and approx.700/sup 0/C, and increased with irradiation dose. A similar enrichment of C occurred on the sample surface over the same temperature range. The surface C enrichment was associated with V/sub 3/C precipitates on the sample surface, while the damage-zone C enrichment was associated with an irradiation-induced coherent )012) habit-plane precipitate.« less
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