Reactor Development Program (Progress Report, March 1966)
- Argonne National Lab. (ANL), Argonne, IL (United States)
The Reactor Development Program Progress Report, issued monthly, is intended to be a means of reporting those items of significant technical progress which have occurred in both the specific reactor projects and the general engineering research and development programs. The report is organized in a way which, it is hoped, gives the clearest, most logical overall view of progress. The budget classification is followed only in broad outline, and no attempt is made to report separately on each sub-activity number. Further, since the intent is to report only items of significant progress, not all activities are reported each month. In order to issue this report as soon as possible after the end of the month editorial work must necessarily be limited. Also, since this is an informal progress report, the results and data presented should be understood to be preliminary and subject to change unless otherwise stated.
- Research Organization:
- Argonne National Laboratory (ANL), Argonne, IL (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); US Atomic Energy Commission (AEC)
- DOE Contract Number:
- W-31109-ENG-38
- NSA Number:
- NSA-20-026394
- OSTI ID:
- 4539125
- Report Number(s):
- ANL-7193
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
42 ENGINEERING
AARR
BURNUP
CHROMIUM ALLOYS
COATING
CRITICALITY
EBR-2
EBR-II
FAST NEUTRONS
FISSION
FUELS
Fast Reactor
IRRADIATION
LIQUID METAL COOLANT
MOCKUP
Nuclear Criticality Safety Program (NCSP)
Nuclear Safety
OPERATION
REPROCESSING
RESEARCH REACTORS
Reactor Physics
SEFOR
TESTING
TREAT
URANIUM 235
URANIUM 238
ZPPR
ZPR-3
ZPR-6
42 ENGINEERING
AARR
BURNUP
CHROMIUM ALLOYS
COATING
CRITICALITY
EBR-2
EBR-II
FAST NEUTRONS
FISSION
FUELS
Fast Reactor
IRRADIATION
LIQUID METAL COOLANT
MOCKUP
Nuclear Criticality Safety Program (NCSP)
Nuclear Safety
OPERATION
REPROCESSING
RESEARCH REACTORS
Reactor Physics
SEFOR
TESTING
TREAT
URANIUM 235
URANIUM 238
ZPPR
ZPR-3
ZPR-6