Jump to main content
United States Environmental Protection Agency
EPA National Library Network
Search Results for the EPA National Library Catalog
Items Found: 16
Showing: Items 1 - 16
Your Search: (SUBJECT=Reactors fast)
Publication dates (newest-oldest)
Publication dates (oldest-newest)
Choose a Library:
(CTRL-CLICK for multiple libraries)
Search all libraries
Capital Group(All DC-area libraries)
CEMM/GEMMD Library/Gulf Breeze,FL
Env Science Center Library/Ft Meade,MD
NVFEL Library/Ann Arbor, MI
OCSPP Chemical Library/Washington,DC
Region 1 Library/Boston,MA
Region 2 Library/New York,NY
Region 3 Library/Philadelphia, PA
Region 4 Library/Atlanta,GA
Region 5 Library/Chicago,IL
Region 6 Library/Dallas,TX
Region 7 IRC Library/Kansas City,KS
Region 8 Technical Library/Denver,CO
Region 9 Library/San Francisco,CA
Region 10 Library/Seattle,WA
Research Triangle Park Library/RTP, NC
Choose a Collection:
(CTRL-CLICK for multiple collections)
Search all collections
Applied Physics Division Annual Report, July 1, 1969-June 30, 1970.
Calculations for a Large Fast Reactor. A Comparison of Results Organised by the International Working Group on Fast Reactors of the International Atomic Energy Agency.
Civil Defense Research Project Annual Progress Report, March 1969-March 1970.
Contribution to Research on the Behavior of Fission Products in Nuclear Fuels by Measurement of the Vapor Pressures of the Constituents of (Upu)O/Sub 2/ Irradiated in a Fast Neutron Flux.
Dynamics of a Fast Reactor with in-Core Thermionic Converters. Fourth Annual Report, September 1, 1969-August 31, 1970.
Experimental Investigation of Loop Caused Influences on Parallel Flow-Induced Vibration of Fuel Pins.
Fuel Element Development for the Gas-Cooled Fast Breeder Reactor. Part I. Sealed Fuel Rod Design.
In-Pile Equipment for Strain Measurements on Nuclear Fuels and Structural Materials.
In-Reactor Restructuring Temperatures and Kinetics for (U,Pu)O/Sub 2/.
Kinetics of a Fast Pulsed Reactor in a Periodic or Quasi-Periodic State.
Lmfbr Physics Programs. Quarterly Technical Progress Report, January-March 1971.
Observations of Fuel-Cladding Chemical Interactions as Applied to Gcbr Fuel Rods.
Results of the Calculation for a Standard Fast Reactor.
Sensitivity of Uranium and Separative Work Requirements to Variations in Reactor Programmes, Reactor Data and Load Characteristics.
Studies on Wear and Frictional Behavior Between Fuel Rod Bundles and Spacer Grids in Sodium.
Uranium availability and the breeder decision /
Save, Print or Email Selected Records
Selected (this page only)
Selected (across pages)
All (this page only)
All (all pages - 500 item maximum)
Text (Brief Information)
Text (Full Information)
Endnote (Endnote Import)
ASCII delimited for EXCEL
to ask a question, provide feedback, or report a problem.
Laws & Regulations