Experimental determinations of the pre- and postirradiation thermal transport and thermal expansion properties of simulated fuel rods for an HTGR
Bibliographic record
Abstract
No abstract is available for this record. The assistant can identify its topic from the title, but cannot infer the study’s results.
Source: Not provided · Quality: missing
Research context
OpenAlex topics: Nuclear reactor physics and engineering · Nuclear Materials and Properties · Graphite, nuclear technology, radiation studies
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (20)
Show source-provided references
1. HTGR Base Program Progress Report for Period 1 July, 1975 to 31 Dec. 1976, ORNL-5274 · 1978
2. Thermal Conductivity of Uranium Dioxide, Report of Panel on Thermal Conductivity of Uranium Dioxide
3. Moore · Nucl. Technol. · 1974 · 22 · 8810.13182/NT74-A16277 ↗
4. Delle · 1974
5. Hamner · 1977
6. Homan · ORNL-5115 · 1976
7. Moore · ORNL-4986 · 1976
8. Laubitz · Metrologia · 1971 · 7 · 110.1088/0026-1394/7/1/002 ↗
9. Holder · ORNL/TM-5539 · 1977
10. Kollie · 1974 · 129
11. Grade NF 6353 graphite (natural flake) from Asbury Graphite Mills.
12. Grade 240 petroleum pitch from Ashland Oil, Inc.
13. Grade GLCC-1008 graphite flour from Great Lakes Carbon Corporation.
14. A spherical carbon black from R.T. Vanderbilt Co. Varcum from Rechhold Chemical Corporation.
15. High Flux Isotope Reactor, Operated at the Oak Ridge National Laboratory.
16. Johnson · GA-A12910 (GA-LTR-9) · 1974
17. Johnson · GA-A13486 · 1975
18. McElroy · ORNL TM-3477 · 1971
19. Kaae · GA-A14052 · 1976
20. Wagner · LA-6181 · 1976