skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: DEVELOPMENT OF URANIUM NITRIDE-STAINLESS STEEL DISPERSION FUEL ELEMENTS

Abstract

In research in support of the GCRE, procedures for the fabrication of stainless steel-clad flat-plate fuel elements having a core of 28 w/o UN dispersed in an iron-18 w/o chromium--14 w/o nickel--2.5 w/o molybdenum matrix were developed. The preparation of UN and its compatibility with the components of the matrix alloy were studied. The UN for the program was prepared by nitriding uranium metal at 850 C and then dissociating the U/sub 2/N/sub 3/ produced to UN in a vacuum at 1300 C. In compatibility studies, UN reacted with nickel alone at 1800 F, but no reaction with nickel was observed when the other matrix components were also present. The effects of fabricational variables were evaluated by metallographic examination, longitudinal and transverse tensile tests, bend tests, and corrosion tests. Studies indicated that minus 200 plus 325-mesh UN dispersed in a minus 325-mesh elemental-powder matrix rolled green vith a 30 per cent initial reduction at 2100 F and then annealed 3 hr at 2300 F produced the best fuel core. (auth)

Authors:
; ; ;
Publication Date:
Research Org.:
Battelle Memorial Inst., Columbus, Ohio
OSTI Identifier:
4252832
Report Number(s):
BMI-1365
NSA Number:
NSA-13-019224
DOE Contract Number:  
W-7405-ENG-92
Resource Type:
Technical Report
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-59
Country of Publication:
United States
Language:
English
Subject:
METALLURGY AND CERAMICS; ANISOTROPY; ANNEALING; CHEMICAL REACTIONS; CORROSION; DISPERSIONS; FABRICATION; FUEL ELEMENTS; GCRE-1; METALLOGRAPHY; NICKEL; PLATES; POWDERS; PREPARATION; PYROLYSIS; REACTORS; ROLLING; STAINLESS STEELS; TENSILE PROPERTIES; URANIUM; URANIUM NITRIDES; VACUUM

Citation Formats

Paprocki, S.J., Keller, D.L., Cunningham, G.W., and Foulds, A.K. Jr. DEVELOPMENT OF URANIUM NITRIDE-STAINLESS STEEL DISPERSION FUEL ELEMENTS. United States: N. p., 1959. Web. doi:10.2172/4252832.
Paprocki, S.J., Keller, D.L., Cunningham, G.W., & Foulds, A.K. Jr. DEVELOPMENT OF URANIUM NITRIDE-STAINLESS STEEL DISPERSION FUEL ELEMENTS. United States. doi:10.2172/4252832.
Paprocki, S.J., Keller, D.L., Cunningham, G.W., and Foulds, A.K. Jr. Fri . "DEVELOPMENT OF URANIUM NITRIDE-STAINLESS STEEL DISPERSION FUEL ELEMENTS". United States. doi:10.2172/4252832. https://www.osti.gov/servlets/purl/4252832.
@article{osti_4252832,
title = {DEVELOPMENT OF URANIUM NITRIDE-STAINLESS STEEL DISPERSION FUEL ELEMENTS},
author = {Paprocki, S.J. and Keller, D.L. and Cunningham, G.W. and Foulds, A.K. Jr.},
abstractNote = {In research in support of the GCRE, procedures for the fabrication of stainless steel-clad flat-plate fuel elements having a core of 28 w/o UN dispersed in an iron-18 w/o chromium--14 w/o nickel--2.5 w/o molybdenum matrix were developed. The preparation of UN and its compatibility with the components of the matrix alloy were studied. The UN for the program was prepared by nitriding uranium metal at 850 C and then dissociating the U/sub 2/N/sub 3/ produced to UN in a vacuum at 1300 C. In compatibility studies, UN reacted with nickel alone at 1800 F, but no reaction with nickel was observed when the other matrix components were also present. The effects of fabricational variables were evaluated by metallographic examination, longitudinal and transverse tensile tests, bend tests, and corrosion tests. Studies indicated that minus 200 plus 325-mesh UN dispersed in a minus 325-mesh elemental-powder matrix rolled green vith a 30 per cent initial reduction at 2100 F and then annealed 3 hr at 2300 F produced the best fuel core. (auth)},
doi = {10.2172/4252832},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1959},
month = {7}
}