Primary Navigation
Secondary Navigation
Content
Contact Us
Home
Search
Explore
About
Help
About this Partner
Explore the holdings of this Partner
Explore all Partners
Country:
United States (3)
Less...
Decade:
1970-1979 (3)
1960-1969 (83)
1950-1959 (40)
Less...
Serial/Series Title:
ANL (Series) (35)
AEC research and development report (14)
Atomic Energy Commission Reports (14)
TID (11)
Argonne National Laboratory Annual Report (3)
More...
Less...
Nuclear technology series (1)
Less...
Search Inside the UNT Libraries Government Documents Department
Everything
|
Text
|
Image
|
Sound
|
Thesis or Dissertation
More
Book
Collection
Dataset
Legal Document
Legislative Document
Letter
Map
Pamphlet
Photograph
Physical Object
Poster
Report
Website
fulltext
metadata
title
subject
creator
Advanced Search
Search Help
You limited your search to:
Partner:
UNT Libraries Government Documents Department
Serial/Series Title:
Argonne National Laboratory Reports
Remove
Results 11 - 34 of 129
|
|
Sort by: Date Added (Newest)
Best Match
Title
Creator
Date Created (Newest)
Date Created (Oldest)
Date Added (Newest)
Date Added (Oldest)
Argonne National Laboratory Annual Report: 1956
The EBWR: Experimental Boiling Water Reactor
The Process Equipment and Protective Enclosures Designed for the Fuel Fabrication Facility: Facility #350
Two-Phase Air-Water Flow Phenomena
Argonne National Laboratory Annual Report: 1958
Selected Values of the Physical Properties of Various Materials
Argonne National Laboratory Annual Report: 1957
Irradiation of an Aluminum Alloy-Clad, Aluminum-Uranium Alloy-Fueled Plate
Lecture Notes on Reactor Shielding
Argonne High-Flux Research Reactor: AHFR Conceptual Design Study
Cost Study of a 100-Mw(e) Direct-Cycle Boiling Water Reactor Plant
Condensation of Metal Vapors: Mercury and the Kinetic Theory of Condensation
Performance Characteristics of a Liquid Metal MHD Generator
A Report on Some Attempts to Cast Centrifugally Fuel Elements of Small Diameter
Midwest Tandem Cyclotron: A Proposal for a Regional Accelerator Facility
A Hybrid-Computer Program for Transient Temperature Calculations on TREAT Fast Reactor Safety Experiments
A Generalized Computer Program for Flowsheet Calculation and Process Data Reduction
LMFBR Nuclear Safety Program Annual Report: July 1, 1969, to June 30, 1970
Liquid MHD Power Cycle Studies
Survey and Status Report on Application of Acoustic-Boiling-Detection Techniques to Liquid-Metal-Cooled Reactors
Pressure-Pulse Propagation in Two-Phase One- and Two-Component Mixtures
Design and Testing of a High-Heat Flux Electron-Bombardment Heater
Calculations on U235 Fission Product Decay Chains
Spectral representation and criticality problem of a two-region cell transport operator
FIRST
PREV
1
2
3
4
5
NEXT
LAST