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Title: PROGRESS RELATING TO CIVILIAN APPLICATIONS DURING MARCH 1959

Abstract

S>In the program on the use of radioisotopes for quslity control in the cement industry, experiments were performed on the determination of Ca by EDTA titration using a radiometric endpoint, on sulfur analysis by radiometric endpoint, and on sulfur analysis by rsdiometric titration with Ba/sup 140/ ae BaCl/sub 2/. Work on the survey and evaluation of various industrial processes which might utilize intrinsic radioisotopes in process control was completed. A study of the solidification of U cast in cylindrical graphite molds is being made. Studies aimed at reducing the amount of additive needed to stabilize UO/sub 2/ were continued. The irrsdiation history of a 2 wt.% U--Zr alloy hydride capsule is reported. Investigation of the changes in the mechanical properties of AISl Type 347 stainless steel as affected by exposure to fast neutron flux is being conducted. The evaluation of selected Nb-base alloys for possible service in pressurized-water reactors was continued. A program to investigate the friction and wear behavior of rubbing surfaces lubricated by high-temperature sedium was initiated. A study of the fabrication characteristics and the mechanical and physical properties of Nb-rich U alloys is being made. Thorium--uranium alloys are being investigated with the objective of improving corrosion resistancemore » and irradiation stability by means of alloying and control of processing variables. A research program to develop a physical model and mathematical theory to describe the release of fission gases from sintered fuel materials is reported. Techniques for producing cements of 90% of theoretical density or better containing 60 to 90 vol.% fuel dispersed in a metal matrix are being investigated. A gaspressure-bending process is being investigated as a method of cladding of ceramic and cermet-type fuels with Mo and Nb. The effects of forming pressure and initial particle size on the perosity and grnin size of UC compacts sintered at 1600 deg C for 1 hr are reported. Work was continued on the pest-irradiation study of fission-gas release from UO/sub 2/-graphite spheres at elevated temperatures. The evalulation of materials of construction for the Darex, SulfexThorex, Darex-Thorex, Zirfex, and Fluoride Volatility processes was continued. The irradiation of capsules containing UC specimens is continuing. Data are presented on the fabricability and hardness of binary Ta alloys. (For . preceding period see BMI-1324). (W.L.H.)« less

Authors:
;
Publication Date:
Research Org.:
Battelle Memorial Inst., Columbus, Ohio
OSTI Identifier:
4158298
Report Number(s):
BMI-1330
NSA Number:
NSA-14-018104
DOE Contract Number:  
W-7405-ENG-92
Resource Type:
Technical Report
Resource Relation:
Other Information: Decl. June 12, 1959. Orig. Receipt Date: 31-DEC-60
Country of Publication:
United States
Language:
English
Subject:
METALS, CERAMICS, AND OTHER MATERIALS; ADDITIVES- CLEANING- STABILITY- URANIUM DIOXIDE; BARIUM CHLORIDES- BARIUM 140- CALCIUM- CEMENTS- CLEANING- CONTROL ELEMENTS- EDTA- MEASURED VALUES- QUALITATIVE ANALYSIS- QUANTITATIVE ANALYSIS- RADIOISOTOPES- RADIOMETERS- SULFUR- THERMAL RADIATION- USES; BONDING- CERAMICS- CERMETS- CLEANING- FUEL CANS- GASES- MOLYBDENUM- NIOBIUM- PRESSURE; CARBIDES- CLEANING- COMPACTS- EFFICIENCY- GRAIN SIZE- HIGH TEMPERATURE- POROSITY- PRESSURE- SINTERING- URANIUM COMPOUNDS; CARBIDES- CLEANING- FUEL CANS- IRRADIATION- URANIUM COMPOUNDS; CASTING- CLEANING- CYLINDERS- GRAPHITE- SOLIDIFICATION- URANIUM; CERMETS- CLEANI

Citation Formats

Dayton, R.W., and Tipton, C.R. Jr. PROGRESS RELATING TO CIVILIAN APPLICATIONS DURING MARCH 1959. United States: N. p., 1959. Web. doi:10.2172/4158298.
Dayton, R.W., & Tipton, C.R. Jr. PROGRESS RELATING TO CIVILIAN APPLICATIONS DURING MARCH 1959. United States. doi:10.2172/4158298.
Dayton, R.W., and Tipton, C.R. Jr. Wed . "PROGRESS RELATING TO CIVILIAN APPLICATIONS DURING MARCH 1959". United States. doi:10.2172/4158298. https://www.osti.gov/servlets/purl/4158298.
@article{osti_4158298,
title = {PROGRESS RELATING TO CIVILIAN APPLICATIONS DURING MARCH 1959},
author = {Dayton, R.W. and Tipton, C.R. Jr.},
abstractNote = {S>In the program on the use of radioisotopes for quslity control in the cement industry, experiments were performed on the determination of Ca by EDTA titration using a radiometric endpoint, on sulfur analysis by radiometric endpoint, and on sulfur analysis by rsdiometric titration with Ba/sup 140/ ae BaCl/sub 2/. Work on the survey and evaluation of various industrial processes which might utilize intrinsic radioisotopes in process control was completed. A study of the solidification of U cast in cylindrical graphite molds is being made. Studies aimed at reducing the amount of additive needed to stabilize UO/sub 2/ were continued. The irrsdiation history of a 2 wt.% U--Zr alloy hydride capsule is reported. Investigation of the changes in the mechanical properties of AISl Type 347 stainless steel as affected by exposure to fast neutron flux is being conducted. The evaluation of selected Nb-base alloys for possible service in pressurized-water reactors was continued. A program to investigate the friction and wear behavior of rubbing surfaces lubricated by high-temperature sedium was initiated. A study of the fabrication characteristics and the mechanical and physical properties of Nb-rich U alloys is being made. Thorium--uranium alloys are being investigated with the objective of improving corrosion resistance and irradiation stability by means of alloying and control of processing variables. A research program to develop a physical model and mathematical theory to describe the release of fission gases from sintered fuel materials is reported. Techniques for producing cements of 90% of theoretical density or better containing 60 to 90 vol.% fuel dispersed in a metal matrix are being investigated. A gaspressure-bending process is being investigated as a method of cladding of ceramic and cermet-type fuels with Mo and Nb. The effects of forming pressure and initial particle size on the perosity and grnin size of UC compacts sintered at 1600 deg C for 1 hr are reported. Work was continued on the pest-irradiation study of fission-gas release from UO/sub 2/-graphite spheres at elevated temperatures. The evalulation of materials of construction for the Darex, SulfexThorex, Darex-Thorex, Zirfex, and Fluoride Volatility processes was continued. The irradiation of capsules containing UC specimens is continuing. Data are presented on the fabricability and hardness of binary Ta alloys. (For . preceding period see BMI-1324). (W.L.H.)},
doi = {10.2172/4158298},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1959},
month = {4}
}