These tools will no longer be maintained as of December 31, 2024. Archived website can be found here. PubMed4Hh GitHub repository can be found here. Contact NLM Customer Service if you have questions.
2. Testing of containment systems used with light-water-cooled power reactors. ORNL-NSIC-26. Zapp FC ORNL-NSIC Rep; 1968 Sep; ():1-258. PubMed ID: 5713433 [No Abstract] [Full Text] [Related]
3. Potential metal-water reactions in light-water-cooled power reactors. ORNL-NSIC-23. McLain HA ORNL-NSIC Rep; 1968 Sep; ():1-201. PubMed ID: 5713432 [No Abstract] [Full Text] [Related]
4. Air cleaning as an engineered safety feature in light-water-cooled power reactors. ORNL-NSIC-25. Keilholtz GW; Guthrie CE; Battle GC ORNL-NSIC Rep; 1968 Sep; ():1-7. PubMed ID: 5713435 [No Abstract] [Full Text] [Related]
5. Review of methods of mitigating spread of radioactivity from a failed containment system. ORNL-NSIC-27. ORNL-NSIC Rep; 1968 Sep; ():1-103. PubMed ID: 5713431 [No Abstract] [Full Text] [Related]
6. United Kingdom nuclear reactor design and operation. Edmondson B Br J Radiol; 1987 Dec; 60(720):1174-7. PubMed ID: 3690166 [No Abstract] [Full Text] [Related]
7. Radiation dosimetry studies at the Health Physics Research Reactor. ORNL-4113. Johnson DR; Poston JW ORNL; 1968 Jan; ():1-65. PubMed ID: 5675801 [No Abstract] [Full Text] [Related]
8. Uranium: health risks from a nuclear power industry. Kerr C Med J Aust; 1977 Oct; 2(18):583-6. PubMed ID: 600186 [No Abstract] [Full Text] [Related]
9. BEHAVIOR OF IODINE IN REACTOR CONTAINMENT SYSTEMS. ORNL-NSIC-4. CONTRACT NO. W-7405-ENG-26. KEILHOLTZ GW; BARTON CJ ORINS Rep US At Energy Comm; 1965 Feb; 59():1-94. PubMed ID: 24547339 [No Abstract] [Full Text] [Related]
11. An isopleth method for population evacuation related to nuclear power reactor accidental release. Bowman WB; Healy KE; Swindle DL Health Phys; 1978 Nov; 35(5):685-91. PubMed ID: 744732 [No Abstract] [Full Text] [Related]
12. The integrity of reactor pressure vessels. ORNL-NSIC-15. Miller EC ORNL-NSIC Rep; 1966 May; ():1-54. PubMed ID: 5936128 [No Abstract] [Full Text] [Related]
13. A realistic field facility to simulate reactor spectra. Taylor GC; Thomas DJ; Bennett A Radiat Prot Dosimetry; 2004; 110(1-4):111-5. PubMed ID: 15353632 [TBL] [Abstract][Full Text] [Related]
14. Estimation of radiation doses following a reactor accident. ORNL-4086. Binford FT; Barish J; Kam FB ORNL; 1968 May; ():1-41. PubMed ID: 5675813 [No Abstract] [Full Text] [Related]
16. The adequacy of scale-up in experiments on fission product behavior in reactor accidents. I. An analysis of scale-up in the U. S. nuclear safety program. ORNL-3901. Miller CE; Browning WE LA Rep; 1966 Jul; ():1-58. PubMed ID: 5300749 [No Abstract] [Full Text] [Related]
17. Devastation in Japan. Current designs address safety problems in Fukushima reactors. Clery D Science; 2011 Mar; 331(6024):1506. PubMed ID: 21436413 [No Abstract] [Full Text] [Related]
18. A new technique for reactor siting dose calculations. Willis CA; Spangler GA; Rhoades WA Health Phys; 1970 Jul; 19(1):47-54. PubMed ID: 5513543 [No Abstract] [Full Text] [Related]
19. EFFECT OF PARTICLE AGGLOMERATION ON THE PENETRATION OF FILTERS UTILIZED WITH DOUBLE CONTAINMENT SYSTEMS. ORNL-NSIC-1. FONTANA MH; BROWNING WE ORINS Rep US At Energy Comm; 1963 Sep; 59():1-20. PubMed ID: 24547337 [No Abstract] [Full Text] [Related]