PROGRESS RELATING TO CIVILIAN APPLICATIONS DURING MAY 1960

PDF Version Also Available for Download.

Description

The investigation of the stabilizing influence of oside additions to UO/ sub 2/ was continued. The effects of fast-neutron irradiation upon the mechanical properties of Type 347 stainless steel are being investigated. Tensile data are reported for alloys of Nb-Cr and Nb-Zr. The major effect of fast-neutron irradiation on the creep properties of Zircaloy-2 is being studied by comparing the in-reactor creep behavior of the alloy with out-of-reactor creep properties. New methods for the determination of low concentrations of oxygen in sodium are being investigated. The mechanisms of wear and friction of various metals in sliding contact in liquid sodium ... continued below

Physical Description

Medium: P; Size: Pages: 100

Creation Information

Dayton, R.W. & Tipton, C.R. Jr. July 12, 1960.

Context

This report is part of the collection entitled: Office of Scientific & Technical Information Technical Reports and was provided by UNT Libraries Government Documents Department to Digital Library, a digital repository hosted by the UNT Libraries. More information about this report can be viewed below.

Who

People and organizations associated with either the creation of this report or its content.

Publisher

Provided By

UNT Libraries Government Documents Department

Serving as both a federal and a state depository library, the UNT Libraries Government Documents Department maintains millions of items in a variety of formats. The department is a member of the FDLP Content Partnerships Program and an Affiliated Archive of the National Archives.

Contact Us

What

Descriptive information to help identify this report. Follow the links below to find similar items on the Digital Library.

Description

The investigation of the stabilizing influence of oside additions to UO/ sub 2/ was continued. The effects of fast-neutron irradiation upon the mechanical properties of Type 347 stainless steel are being investigated. Tensile data are reported for alloys of Nb-Cr and Nb-Zr. The major effect of fast-neutron irradiation on the creep properties of Zircaloy-2 is being studied by comparing the in-reactor creep behavior of the alloy with out-of-reactor creep properties. New methods for the determination of low concentrations of oxygen in sodium are being investigated. The mechanisms of wear and friction of various metals in sliding contact in liquid sodium are being studied. Data are presented on corrosion properties, short-time tensile properties, stress-rupture properties, and electrical resistivity for Nb--U alloys. The development of Th and Th--U alloys with improved radiation resistance is being investigated. A program is reported for the determination of diffusion coefficients of Xe in single-crystal UO/sub 2/ specimens and the in-pile study of fission-product release from sintered UO/sub 2/. Thermal-conductivity, thermal-expansion, electrical-resistivity, and modulus-of-rupture measurements are being made on 80 vol.% UO/sub 2/ cermets. Techniques for the fabrication of compartmented Mo- and Nbclad UO/sub 2/ and cermet fuels are being investigated. Compaction studies of UO/sub 2/ were undertaken to provide core materials which will achieve a range of desired densities on pressure bonding. The fabrication of Type 304 stainiess steel-clad UO/sub 2/ rod, tube, and flat-plate elements and flat-plate assemblies was accomplished by gas pressure bonding. Various methods for economically producing dense UC components by powder-metallurgical techniques are being investigated. A study of the properties of UC is under way. Thermal-gradient experiments are being performed to establish a theoretical basis for the prediction of hydrogen migration in zirconium hydride. Experiments were continued in producing single crystals of UO/sub 2/. Portland cement samples were analyzed for sulfate content using a radiometric method involving the precipitation of Sr/sup 89/SO/sub 4/. Solution-annealed strips of welding alloys for use with Hastelloy F to contain decladding solutions were prepared for welding and corrosion evaluations. A study is being made of the effects of irradiation on cladding- amd core-dissolution processes. Uranium carbide shot was coated with 160 ation of carbon by the thermal decomposition of acetylene in a fluidized bed of the shot. Two programs concerned with investigations of Ta and Ta-base materials of interest for containment of molten Pu-alloy fuels are under way. Fission-gas release from BeO--UO/sub 2/ is being investigated by heat treating neutron-activated sintered pellets. A study of the radiation stability of ceramic-type fuels under conditions simulating those of the MGCR design is in progress. Purther experimental and theoretical studies were carried out to determine the feasibility of coating and preparing U and Th carbides by vapor deposition reactions in a fluidized bed. Methods are being developed for preparing instrumented fuel plates for use in 8M-1 type fuel elements for in-pile test evaluation. Materials were selected and techniques were established for the fabrication of SM-2 reference fuel elements. For the ML- I Reactor Hastelloy X will be used as the fuel-element cladding material. (For preceding penicd see BMI-1434.) (W.L.H.)

Physical Description

Medium: P; Size: Pages: 100

Notes

NTIS

Source

  • Other Information: Orig. Receipt Date: 31-DEC-60

Language

Item Type

Identifier

Unique identifying numbers for this report in the Digital Library or other systems.

  • Report No.: BMI-1442(Rev.)
  • Grant Number: None
  • DOI: 10.2172/4177197 | External Link
  • Office of Scientific & Technical Information Report Number: 4177197
  • Archival Resource Key: ark:/67531/metadc870313

Collections

This report is part of the following collection of related materials.

Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.

What responsibilities do I have when using this report?

When

Dates and time periods associated with this report.

Creation Date

  • July 12, 1960

Added to The UNT Digital Library

  • Sept. 16, 2016, 12:32 a.m.

Description Last Updated

  • Nov. 18, 2016, 7:24 p.m.

Usage Statistics

When was this report last used?

Yesterday: 0
Past 30 days: 0
Total Uses: 1

Interact With This Report

Here are some suggestions for what to do next.

Start Reading

PDF Version Also Available for Download.

Citations, Rights, Re-Use

Dayton, R.W. & Tipton, C.R. Jr. PROGRESS RELATING TO CIVILIAN APPLICATIONS DURING MAY 1960, report, July 12, 1960; Columbus, Ohio. (digital.library.unt.edu/ark:/67531/metadc870313/: accessed April 23, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.