Filters
Results 1 - 10 of 2114
Results 1 - 10 of 2114.
Search took: 0.024 seconds
Sort by: date | relevance |
AbstractAbstract
No abstract available
Primary Subject
Source
Berman, B.L. (ed.); California Univ., Livermore (USA). Lawrence Livermore Lab; p. 657-658; 1973
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Primary Subject
Source
ANS winter meeting; San Francisco, CA, USA; 27 Nov 1977; See CONF-771109--. Published in summary form only.
Record Type
Journal Article
Literature Type
Conference
Journal
Transactions of the American Nuclear Society; v. 27 p. 828-829
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Doucette, C.O.; Jensen, A.M.; Colling, D.W.
EG and G Idaho, Inc., Idaho Falls (USA)1982
EG and G Idaho, Inc., Idaho Falls (USA)1982
AbstractAbstract
[en] This paper describes the unique and diverse test capabilities of the Power Burst Facility (PBF). The PBF test reactor, located at the Idaho National Engineering Laboratory (INEL), simulates normal, off-normal, and accident operating conditions of light water reactor fuel rods. Capabilities of the PBF are illustrated by brief discussions of the types of tests performed at the facility. These include a wide range of experiments to help resolve key safety issues concerning light water reactors, assess computer models, and confirm adequacy of specific Nuclear Regulatory Commission licensing regulations
Primary Subject
Source
1982; 12 p; Topical meeting on fast, thermal and fusion reactor experiments; Salt Lake City, UT (USA); 12 - 15 Apr 1982; CONF-820406--17; Available from NTIS., PC A02/MF A01 as DE82017730
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Primary Subject
Source
Anon; p. 39-40; 1974; Univ. of Virginia; Charlottesville, VA; Conference on research, test and training reactors; Charlottesville, Virginia, USA; 12 Aug 1974
Record Type
Book
Literature Type
Conference
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Brenner, D.S.; Chrien, R.E.; Gill, R.; Stelts, M.; Hill, J.C.; Wohn, F.K.
Clark Univ., Worcester, MA (USA); Brookhaven National Lab., Upton, NY (USA); Ames Lab., IA (USA)1979
Clark Univ., Worcester, MA (USA); Brookhaven National Lab., Upton, NY (USA); Ames Lab., IA (USA)1979
AbstractAbstract
[en] The installation of the mass separator TRISTAN, on-line at the Brookhaven HFBR will be reviewed with emphasis placed on recent developments
Primary Subject
Source
1979; 10 p; International symposium on future directions in studies of nuclei far from stability; Nashville, TN, USA; 10 - 13 Sep 1979; CONF-790976--5; Available from NTIS., PC A02/MF A01
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Miller, L.F.
Tennessee Univ., Knoxville (USA); Oak Ridge National Lab., TN (USA)1982
Tennessee Univ., Knoxville (USA); Oak Ridge National Lab., TN (USA)1982
AbstractAbstract
[en] Control of the Oak Ridge Research Reactor Pool Side Facility (ORR-PSF) pressure vessel surveillance irradiation experiment temperature is implemented by digital computer control of electrical heaters under fixed cooling conditions. Cooling is accomplished with continuous flows of water in pipes between specimen sets and of helium-neon gas in the specimen set housings. Control laws are obtained from solutions of the discrete-time Riccati equation and are implemented with direct digital control of solid state relays in the electrical heater circuit. Power dissipated by the heaters is determined by variac settings and the percent of time that the solid state relays allow power to be supplied to the heaters. Control demands are updated every forty seconds
Primary Subject
Source
1982; 14 p; 4. ASTM-EURATOM symposium on reactor dosimetry; Gaithersburg, MD, USA; 22 - 26 Mar 1982; Available from NTIS., PC A02/MF A01 as DE82011529
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Primary Subject
Source
Transactions of the American Nuclear Society conference on reactor operating experience; Chattanooga, TN, USA; 7 Aug 1977; Published in summary form only.
Record Type
Journal Article
Literature Type
Conference
Journal
Transactions of the American Nuclear Society. Supplement; v. 26(1); p. 36-37
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Primary Subject
Source
ANS annual meeting; San Diego, CA, USA; 18 Jun 1978; See CONF-780622--. Published in summary form only.
Record Type
Journal Article
Literature Type
Conference
Journal
Transactions of the American Nuclear Society; v. 28 p. 705-707
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Gavars, V.V.; Dindun, A.S.; Mikel'son, A.Eh.; Tomson, Eh.Ya.; Platatsis, Eh.Ya.; Kramer, M.M.
AN Latvijskoj SSR, Riga. Inst. Fiziki1970
AN Latvijskoj SSR, Riga. Inst. Fiziki1970
AbstractAbstract
[en] A radiation circuit is suggested, involving a radiation source situated in the nuclear reactor core and the targets placed at a certain distance from the source and shielded from neutron radiation. Between the source and the targets there circulates a substance (indium, manganese, etc.) activated by neutron radiation. The substance then decomposes and yields gamma-radiation. To simplify the design and to increase reliability the circuit is equipped by a mixing chamber connected with the outlets of the source, the targets and the melt collector. The chamber is designed for complete mixing of the circulating substance flows, this making it possible to refuse of remote controled valves, usually used at the inlet and outlet sections of the circuit
Original Title
Mnogoobluchatel'nyj radiatsionnyj kontur
Primary Subject
Source
13 Apr 1970; 2 p; SU PATENT DOCUMENT 321172/A/
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] The design features of the TREAT Vessel Assembly were reviewed with program participants to coordinate special requirements of organizations and facilities. Consideration was given to design configurations that impacted requirements for assembly, handling, shipping and testing
Primary Subject
Source
24 Feb 1978; 23 p; Available from NTIS., PC A02/MF A01 as DE82008059
Record Type
Report
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
1 | 2 | 3 | Next |