Tests made on a 45-MW model of the Phenix steam generator at the CGVS (high- capacity testing unit for sodium-heated steam generators)
Journal Article
·
· Trans. Amer. Nucl. Soc., v. 17, pp. 382-384
OSTI ID:4394167
From joint meeting of the American Nuclear Society and the Atomic Industrial Forum and Nuclear Energy Exhibition; San Francisco, California, USA (11 Nov 1973). See CONF-731101-.
- Research Organization:
- Electricite de France, Paris
- NSA Number:
- NSA-29-006938
- OSTI ID:
- 4394167
- Journal Information:
- Trans. Amer. Nucl. Soc., v. 17, pp. 382-384, Journal Name: Trans. Amer. Nucl. Soc., v. 17, pp. 382-384; ISSN TANSA
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
Similar Records
Texture studies on EBR-II, MARK-II driver fuel
Theoretical and experimental study of Phenix steam generator prototype modules
Sodium expulsion test in a 7-pin geometry
Journal Article
·
Wed Oct 31 23:00:00 EST 1973
· Trans. Amer. Nucl. Soc., v. 17, pp. 217-218
·
OSTI ID:4393858
Theoretical and experimental study of Phenix steam generator prototype modules
Journal Article
·
Wed Oct 31 23:00:00 EST 1973
· Trans. Amer. Nucl. Soc., v. 17, pp. 381-382
·
OSTI ID:4394173
Sodium expulsion test in a 7-pin geometry
Journal Article
·
Wed Oct 31 23:00:00 EST 1973
· Trans. Amer. Nucl. Soc., v. 17, pp. 344-345
·
OSTI ID:4392391