HTGR analytical methods and design verification [electronic resource].
- Published
- Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1982.
- Physical Description
- Pages: 10 : digital, PDF file
- Additional Creators
- United States. Department of Energy. Office of Scientific and Technical Information
Access Online
- Restrictions on Access
- Free-to-read Unrestricted online access
- Summary
- Analytical methods for the high-temperature gas-cooled reactor (HTGR) include development, update, verification, documentation, and maintenance of all computer codes for HTGR design and analysis. This paper presents selected nuclear, structural mechanics, seismic, and systems analytical methods related to the HTGR core. This paper also reviews design verification tests in the reactor core, reactor internals, steam generator, and thermal barrier.
- Report Numbers
- E 1.99:ga-a-16755
E 1.99: conf-820915-1
conf-820915-1
ga-a-16755 - Subject(s)
- Other Subject(s)
- Note
- Published through SciTech Connect.
05/01/1982.
"ga-a-16755"
" conf-820915-1"
"DE82016251"
BNES international conference on gas cooled reactors today, Bristol, UK, 20 Sep 1982.
Neylan, A.J.; Northup, T.E.
General Atomic Co., San Diego, CA (USA) - Funding Information
- AT03-76ET35301
View MARC record | catkey: 14801411