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Title: METALLURGY DIVISION ANNUAL REPORT FOR 1961

Abstract

8 < 8 7 8 7 < 5 8 6 ; : 9: 2 8 9 9 ; ; < 9 : 9 : 8 8 I of transformation and fusion, of U and U- fissium alloys were completed during the year. Data are also included on cladding penetration by molten U-fissium alloys and molten Pu fuel. Irradiation studies of U-fissium and Ufissium-Zr alloys were conducted. Progress is reported on the development of methods and equipment for remote refabrication of EBR-II fuel. Development and Fabrication of EBR-I Core IV Fuel Elements. A program to investigate methods of fabricating Pu-Al reference alloy for EBR-I Core IV is described along with the production of fuel rods for this core. The procurement, fabrication, and inspection of components other than Ra material for Core N of EBR-I was continued. Data obtained in nondestructive inspection of EBR-I Core IV components are presented along with data concerning properties of and radiation effects on Al-Pu alloys. EBWR Fabrication Programs. The work in these programs was largely concenned with fabrication of a control-rod-drive assembly made of 17- 4 PH stainless steel. Fabrication of Borax-V Boiling and Superheater Fuel Elements, Control Rod Drive Shafts, and Control Rods. Data aremore » given on fabrication and evaluation of Borax-V superheat fuel elements. Information on new extension shafts for Borax-V control rod drives and on Borax-V control rods is included. Fabrication of Converter Plates for JANUS Biology Reactor. The plates were fabricated from vacuum cast Al-9.5 wt % U, 93% enriched alloy. A flow sheet which shows the fabrication procedure is included. Development of Ceramic Fuel and High-Absorbing Materials. Progress is reported in studies concerning the properties of PuC, PuC-UC systems, fueled glasses, and poison glasses. Other work is reported on investigations of UO/sub 2/, uranium oxidelanthanum oxide systems, uranium oxide-neodymium oxide systems, urania- thoria systems, and U-thorium sulfide systems. Irradiation Evaluation of Various Experimental Fuel, Control, and Structural Materials. Effort was devoted to irradiations of ThO/sub 2/-UO/sub 2/ pellets, irradiations of ZrO/sub 2/-UO/sub 2/ -CaO pellets, irradiations of UO/sub 2/ pellets with collapsed Al alloy cladding, irradiation of PuC and PuC-UC systems, post-irradiation annealing of Al-17.5 wt% U alloy, and Al-39 wt% U/sub 3/O/sub 8/ dispersion, irradiation of hightemperature fuel alloys, and irradiation of prototype SL-1 fuel plates. Other work is reported on the development of techniques for measurement of fission gas release from oxide fuels, development of metallographic techniques for fuels, and development of a pinhole-camera autoradiographic teclurique. Examination of Full-scale Reactor Fuel Elements and Control Rods. Activities include examination of EBR-I, MK III fuel rods, post-irradiation examination of Borax-II and -IV control rods, and measurement of water channel gaps in EBWR Core 1A fuel elements. Development of Corrosion-Resistant Jacketing and Structural Materials. Efforts were devoted to obtaining a high-temperature creep-resistant Al powder-product tubing, development of Ti-Zr alloys for use in superheated steam, evaluating corrosion of ferrous materials in water, corrosion of stainless steel in superheated steam, and in vestigation of Ti and Ti alloys for use with hightemperature Hg. Nondestructive Testing Development. Developmental investigations are reported on ultrasonic techniques, eddy current techniques, neutron techniques, x-ray radiography, and scintillation spectrometry. Miscellaneous Developments. Information is presented on operation and modification of the ANL-2 high-pressure water loop, Pu foil fabrication, and Zr tubing fabrication. Metallurgy of U and Its Alloys. Investigations are reported on the temperature dependence of elastic moduli in alpha U single crystals, crystallographic structure of alpha U« less

Publication Date:
Research Org.:
Argonne National Lab., Ill.
OSTI Identifier:
4768377
Report Number(s):
ANL-6516
NSA Number:
NSA-16-030717
DOE Contract Number:  
W-31-109-ENG-38
Resource Type:
Technical Report
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-62
Country of Publication:
United States
Language:
English
Subject:
METALS, CERAMICS, AND OTHER MATERIALS; ABSORPTION; ALLOYS; ALUMINUM; ALUMINUM ALLOYS; ANNEALING; BOILING; BORAX- 3; BORAX-4; BORAX-5; CALCIUM OXIDES; CAMERAS; CARBIDES; CARBON MONOXIDE; CERAMICS; CHROMIUM OXIDES; COBALT ALLOYS; CONTROL ELEMENTS; COPPER COMPOUNDS; CORROSION; CREEP; CRYSTALS; DEFORMATION; DIFFRACTION; DIFFUSION; DISPERSIONS; DISTRIBUTION; EBR-1; EDDY CURRENTS; EFFICIENCY; ELASTICITY; ELECTROLYSIS; ELECTRON MICROSCOPY; ENRICHMENT; FABRICATION; FAILURES; FILMS; FISSION; FISSION PRODUCTS; FOILS; FUEL CANS; FUEL ELEMENTS; FUELS; FUSION HEAT; GASES; GLASS; GOLD; HIGH TEMPERATURE; HYDROGEN; INSPECTION; INSTRUMENTS; INTERMETALLIC COMPOUNDS; IRON ALLOYS; IRRADIATION; LANTHA

Citation Formats

. METALLURGY DIVISION ANNUAL REPORT FOR 1961. United States: N. p., 1962. Web. doi:10.2172/4768377.
. METALLURGY DIVISION ANNUAL REPORT FOR 1961. United States. https://doi.org/10.2172/4768377
. Wed . "METALLURGY DIVISION ANNUAL REPORT FOR 1961". United States. https://doi.org/10.2172/4768377. https://www.osti.gov/servlets/purl/4768377.
@article{osti_4768377,
title = {METALLURGY DIVISION ANNUAL REPORT FOR 1961},
author = {},
abstractNote = {8 < 8 7 8 7 < 5 8 6 ; : 9: 2 8 9 9 ; ; < 9 : 9 : 8 8 I of transformation and fusion, of U and U- fissium alloys were completed during the year. Data are also included on cladding penetration by molten U-fissium alloys and molten Pu fuel. Irradiation studies of U-fissium and Ufissium-Zr alloys were conducted. Progress is reported on the development of methods and equipment for remote refabrication of EBR-II fuel. Development and Fabrication of EBR-I Core IV Fuel Elements. A program to investigate methods of fabricating Pu-Al reference alloy for EBR-I Core IV is described along with the production of fuel rods for this core. The procurement, fabrication, and inspection of components other than Ra material for Core N of EBR-I was continued. Data obtained in nondestructive inspection of EBR-I Core IV components are presented along with data concerning properties of and radiation effects on Al-Pu alloys. EBWR Fabrication Programs. The work in these programs was largely concenned with fabrication of a control-rod-drive assembly made of 17- 4 PH stainless steel. Fabrication of Borax-V Boiling and Superheater Fuel Elements, Control Rod Drive Shafts, and Control Rods. Data are given on fabrication and evaluation of Borax-V superheat fuel elements. Information on new extension shafts for Borax-V control rod drives and on Borax-V control rods is included. Fabrication of Converter Plates for JANUS Biology Reactor. The plates were fabricated from vacuum cast Al-9.5 wt % U, 93% enriched alloy. A flow sheet which shows the fabrication procedure is included. Development of Ceramic Fuel and High-Absorbing Materials. Progress is reported in studies concerning the properties of PuC, PuC-UC systems, fueled glasses, and poison glasses. Other work is reported on investigations of UO/sub 2/, uranium oxidelanthanum oxide systems, uranium oxide-neodymium oxide systems, urania- thoria systems, and U-thorium sulfide systems. Irradiation Evaluation of Various Experimental Fuel, Control, and Structural Materials. Effort was devoted to irradiations of ThO/sub 2/-UO/sub 2/ pellets, irradiations of ZrO/sub 2/-UO/sub 2/ -CaO pellets, irradiations of UO/sub 2/ pellets with collapsed Al alloy cladding, irradiation of PuC and PuC-UC systems, post-irradiation annealing of Al-17.5 wt% U alloy, and Al-39 wt% U/sub 3/O/sub 8/ dispersion, irradiation of hightemperature fuel alloys, and irradiation of prototype SL-1 fuel plates. Other work is reported on the development of techniques for measurement of fission gas release from oxide fuels, development of metallographic techniques for fuels, and development of a pinhole-camera autoradiographic teclurique. Examination of Full-scale Reactor Fuel Elements and Control Rods. Activities include examination of EBR-I, MK III fuel rods, post-irradiation examination of Borax-II and -IV control rods, and measurement of water channel gaps in EBWR Core 1A fuel elements. Development of Corrosion-Resistant Jacketing and Structural Materials. Efforts were devoted to obtaining a high-temperature creep-resistant Al powder-product tubing, development of Ti-Zr alloys for use in superheated steam, evaluating corrosion of ferrous materials in water, corrosion of stainless steel in superheated steam, and in vestigation of Ti and Ti alloys for use with hightemperature Hg. Nondestructive Testing Development. Developmental investigations are reported on ultrasonic techniques, eddy current techniques, neutron techniques, x-ray radiography, and scintillation spectrometry. Miscellaneous Developments. Information is presented on operation and modification of the ANL-2 high-pressure water loop, Pu foil fabrication, and Zr tubing fabrication. Metallurgy of U and Its Alloys. Investigations are reported on the temperature dependence of elastic moduli in alpha U single crystals, crystallographic structure of alpha U},
doi = {10.2172/4768377},
url = {https://www.osti.gov/biblio/4768377}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1962},
month = {10}
}