624 Matching Results

Search Results

Advanced search parameters have been applied.
in subjects: "materials"  
Results: 1 - 24 next
open access

Defects in metal crystals. Progress report, May 1, 1973--April 30, 1974

Description: Progress was made in the following areas: FIM (field ion microscopy) studies of defects in W irradiated with W ions or electrons; FIM studies of Au irradiated with Au or Xe ions; FIM and electrical resistivity study of vacancy defects in quenched W; FIM studies of dilute Pt alloys; measurement of the range of focused replacement sequences in Au; investigation of grain boundary strtucture (using Au); FIM observation of dissociated screw dislocations in Mo; calculation of properties of point defe… more
Date: January 1, 1974
Creator: Balluffi, R.W. & Seidman, D.N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Once-through steam generator (OTSG) materials and water chemistry. [PWR]

Description: Materials and water chemistry research results associated with the development of the Oconee-1 Reactor steam generator are presented. A summary of water chemistry data acquired during preoperational testing and power operation to date is also included. These data confirm the operational practicality of the nuclear once-through concept using volatile water treatment and high purity condensate demineralized feedwater.
Date: January 1, 1974
Creator: Pocock, F.J. & Levstek, D.F.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Design requirements for uranium ion exchange from acidic solutions in a fluidized system

Description: A fluidized, countercurrent ion-exchange system was developed, operated, and evaluated by the Bureau of Mines in support of its objective to help assure an adequate uranium supply for future national needs. The system consisted of integrated multiple-compartment absorption and elution columns in which the solution flows are continuous, except for short periods when resin increments are withdrawn. The exchange of uranyl sulfate between a simulated acid-leach-uranium solution and a strong-base, i… more
Date: January 1, 1974
Creator: Traut, D.E.; Nichols, I.L. & Seidel, D.C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Permeability and solubility of gases for FFTF/CRBRP cover-gas-seal materials

Description: The permeability (anti P) and diffusion coefficient (D) of the gases H/sub 2/, Ar, Kr and Xe have been measured in certain elastomer materials of interest to the FFTF/CRBRP Cover Seal Program. These elastomers include Buna N, Buna S, Butyl Rubber, ethylene-propylene polyacrylic, polyurethane and silicone. Measurements were made over the temperature range 100 to 300/sup 0/F. Data for the permeability and diffusion coefficient for these gases in the above elastomer materials are given. The method… more
Date: January 1, 1974
Creator: Darnell, A. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Cover gas seals: FFTF-LMFBR seal test program

Description: The objectives of this program are to: (1) conduct static and dynamic tests to demonstrate or determine the mechanical performance of full-size (cross section) FFTF fuel transfer machine and reactor vessel head seals intended for use in a sodium vapor-inert gas environment, (2) demonstrate that these FFTF seals or new seal configurations provide acceptable fission product and cover gas retention capabilities at Clinch River Breeder Reactor Plant (CRBRP) operating environmental conditions other … more
Date: January 1, 1974
Creator: Kurzeka, W.; Oliva, R.; Welch, T.S. & Shimazaki, T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Relationships Between Fracture Toughness and Other Material Properties. Final Report

Description: The key experimental and analytical studies which have led to our present understanding of the mechanisms of ductile fracture are reviewed. It is concluded that insufficient progress has been made in the quantitative description of ductile separation mechanisms on a microscale to allow the realistic prediction of fracture toughness from material properties and microstructure. An experimental study of ductile fracture is underway which has the aim of determining the growth rate of voids in known… more
Date: January 1, 1974
Creator: Perra, M. & Finnie, I.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Experimental Geothermal Research Facilities study (Phase 0). Final report. Volume 1

Description: Phase 0 of a project for Experimental Geothermal Research Facilities focuses on identification of a representative liquid-dominated geothermal reservoir of moderate temperature and salinity, preliminary engineering design of an appropriate energy conversion system, identification of critical technology, and planning for implementation of experimental facilities. The objectives included development of liaison with the industrial sector, to ensure responsiveness to their views in facility require… more
Date: December 31, 1974
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Radioactive zinc ( sup 65 Zn), zinc, cadmium, and mercury in the Pacific Hake, Merluccius productus (Ayres), off the West Coast of the United States

Description: The Pacific Hake, Merluccius productus (Ayers) was used to monitor the waters off Puget Sound and the West Coast of the US for zinc(Zn), cadmium(Cd), mercury(Hg) and {sup 65}Zn. The Columbia River is not the source of Zn, Cd or Hg contamination, but is the source of {sup 65}Zn, with the concentration in the Hake reflecting the position of the Columbia River plume. Zn and Cd accumulation in the Hake were fit to the equation Y=B{sub 1}+B{sub 2}e{sup B}{sub 3}X where Y is the concentration of the … more
Date: June 1, 1974
Creator: Naidu, J.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Seal, dynamic inflatable, development test, installation and removal of

Description: This specification establishes the requirements and procedures (using epoxy adhesive) for the installation and removal of the dynamic inflatable test seal for the Fast Flux Test Facility (FFTF), In-Vessel Handling Machine (IVHM) Reactor Refueling Plug (RRP).
Date: June 10, 1974
Creator: Deboi, H.H. & Ferrante, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Mini-Brayton economic RTG study. Final report

Description: The objective of this study is to demonstrate the applicability of a radioisotope heated Mini-Brayton power system to the 1973 USAF/AEC requirements established for the SURVSATCOM Mission. The principal requiremenets of the power system, are: 400 We power level; maximum weight 205 lbs.; $1.2 to 2.0 million per unit cost; and 5y mission duration. A radioisotope heat source that meets the ACE Nuclear Safety Criteria is presented. The major aspects of the Reference Design MB-ERTG are summarized. T… more
Date: January 1, 1974
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Experimental geothermal research facilities study (Phase O). Final report No. 26405-6001-RU-00

Description: This study focuses on identification of a representative liquid-dominated geothermal reservoir of moderate temperature and salinity, preliminary design of an appropriate energy conversion system, identification of critical technology and planning for the implementation of experimental facilities. Results of Phase O of the project are reported in two volumes. Volume II presents detailed results of studies and analyses arranged in nine appendices including the final report by a subcontractor on t… more
Date: December 31, 1974
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
Back to Top of Screen