Reactor Development Quarterly Progress Report Page: 4 of 64
This report is part of the collection entitled: Office of Scientific & Technical Information Technical Reports and was provided to UNT Digital Library by the UNT Libraries Government Documents Department.
Extracted Text
The following text was automatically extracted from the image on this page using optical character recognition software:
3
TABLE OF CONTENTS
Page
I. PLUTONIUM POWER REACTOR PROGRAM. . . . . . . . . . . 6
A. Boiling Experimental Reactor. . . . . . . . . . . . . . . . . . 6
1. General Design . . . . . . . . . . . . . . . . . . . . . . . . . 6
2. Building . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6
3. Reactor . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7
4. Power Plant . . . . . . . . . . . . . . . . . . . . . . . . . . . 8
B. Borax II......... . . . . . . . . . . . . . . . . . . . . ...- 9
C. BER Fuel Elements . . . . . . . . . . . . . . . . . . . . . . . 11
1. Corrosion Resistant U Alloys. . . . . . . . . . . . . . . . 11
2. Alloy Castings. . . . . . . . . . . . . . . . . . . . . . . . . . 12
3. Fuel Plate Fabrication . . . . . . . . . . . . . . . . . . . . 13
4. End Closures for BER Fuel Plates . . . . . . . . . . . . 13
5. Corrosion of Unclad U Alloys. . . . . . . . . . . . . . . . 14
6. Corrosion Tests of Zircaloy-II Clad, High-U
Alloy Core Plates . . . . . . . . . . . . . . . . . . . . . . 14
7. Thermal Conductivity of U Base Alloys . . . . . . . . . 14
8. Dimensional Stability . . . . . . . . . . . . . . . . . . . . . 14
9. Corrosion-Irradiation Tests of High-U Alloy Pins . 16
D. Engineering Development. . . . . . . . . . . . . . . . . . . . . 19
1. 600-psia Multi-Channel Natural Circulation
Boiling Density Tests . . . . . . . . . . . . . . . . . . . . 19
2. BER Entrainment Studies . . . . . . . . . . . . . . . . .. 19
3. Reactor Core Structure. . . . . . . . . . . . . . . . 19
4. Control Rod Drive Mechanism . . . . . . . . . . . . . . . 23
5. Filter Tests . . . . . . . . . . . . . . . . . . . . . ...... 24
6. Aqueous Corrosion Tests of Al. . . . . . . . ... 24
II. FAST BREEDER REACTOR PROGRAM ...... ..... . .. 30
A. EBR-II..................... .. ....... .. 30
B. EBR-II Working Model - Primary System. . . . . 31
C. Calculations on Fast -Reactors . 32
1. Long Term Changes . . . .'. . . . . . . . . . . . . . . . . . 32
2. Reactivity Coefficients Associated with
Temperature Changes. ................... 36
. 0 . . 0 0 0
Upcoming Pages
Here’s what’s next.
Search Inside
This report can be searched. Note: Results may vary based on the legibility of text within the document.
Tools / Downloads
Get a copy of this page or view the extracted text.
Citing and Sharing
Basic information for referencing this web page. We also provide extended guidance on usage rights, references, copying or embedding.
Reference the current page of this Report.
Reactor Development Quarterly Progress Report, report, January 31, 1955; Lemont, Illinois. (https://digital.library.unt.edu/ark:/67531/metadc1023471/m1/4/: accessed April 25, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.