|
|
|
|
| LEADER |
00000nam a22000003u 4500 |
| 001 |
b7709205 |
| 003 |
CoU |
| 005 |
20131211000000.0 |
| 006 |
m o d f |
| 007 |
cr ||||||||||| |
| 008 |
140422e19820501alu o| f1|||||eng|d |
| 035 |
|
|
|a (TOE)ost5061063
|
| 035 |
|
|
|a (TOE)5061063
|
| 040 |
|
|
|a TOE
|c TOE
|
| 049 |
|
|
|a GDWR
|
| 072 |
|
7 |
|a 21
|2 edbsc
|
| 086 |
0 |
|
|a E 1.99: conf-820915-2
|
| 086 |
0 |
|
|a E 1.99:ga-a-16746
|
| 086 |
0 |
|
|a E 1.99: conf-820915-2
|
| 088 |
|
|
|a ga-a-16746
|
| 088 |
|
|
|a conf-820915-2
|
| 245 |
0 |
0 |
|a HTGR nuclear heat source component design and experience
|h [electronic resource]
|
| 260 |
|
|
|a Normal, Ala. :
|b Alabama A & M University ;
|a Oak Ridge, Tenn. :
|b distributed by the Office of Scientific and Technical Information, U.S. Department of Energy,
|c 1982.
|
| 300 |
|
|
|a Pages: 6 :
|b digital, PDF file.
|
| 336 |
|
|
|a text
|b txt
|2 rdacontent.
|
| 337 |
|
|
|a computer
|b c
|2 rdamedia.
|
| 338 |
|
|
|a online resource
|b cr
|2 rdacarrier.
|
| 500 |
|
|
|a Published through SciTech Connect.
|
| 500 |
|
|
|a 05/01/1982.
|
| 500 |
|
|
|a "ga-a-16746"
|
| 500 |
|
|
|a " conf-820915-2"
|
| 500 |
|
|
|a "DE82016250"
|
| 500 |
|
|
|a BNES international conference on gas cooled reactors today, Bristol, UK, 20 Sep 1982.
|
| 500 |
|
|
|a Simon, W.A.; Peinado, C.O.; Wunderlich, R.G.
|
| 520 |
3 |
|
|a The high-temperature gas-cooled reactor (HTGR) nuclear heat source components have been under design and development since the mid-1950's. Two power plants have been designed, constructed, and operated: the Peach Bottom Atomic Power Station and the Fort St. Vrain Nuclear Generating Station. Recently, development has focused on the primary system components for a 2240-MW(t) steam cycle HTGR capable of generating about 900 MW(e) electric power or alternately producing high-grade steam and cogenerating electric power. These components include the steam generators, core auxiliary heat exchangers, primary and auxiliary circulators, reactor internals, and thermal barrier system. A discussion of the design and operating experience of these components is included.
|
| 536 |
|
|
|b AT03-76SF70046.
|
| 650 |
|
7 |
|a Energy Systems.
|2 local.
|
| 650 |
|
7 |
|a Cogeneration.
|2 local.
|
| 650 |
|
7 |
|a Primary Coolant Circuits.
|2 local.
|
| 650 |
|
7 |
|a Cooling Systems.
|2 local.
|
| 650 |
|
7 |
|a Reactors.
|2 local.
|
| 650 |
|
7 |
|a Steam Generation.
|2 local.
|
| 650 |
|
7 |
|a Graphite Moderated Reactors.
|2 local.
|
| 650 |
|
7 |
|a Specifications.
|2 local.
|
| 650 |
|
7 |
|a Power Generation.
|2 local.
|
| 650 |
|
7 |
|a Reactor Internals.
|2 local.
|
| 650 |
|
7 |
|a Reactor Components.
|2 local.
|
| 650 |
|
7 |
|a Reactor Cooling Systems.
|2 local.
|
| 650 |
|
7 |
|a Htgr Type Reactors.
|2 local.
|
| 650 |
|
7 |
|a Process Heat Reactors.
|2 local.
|
| 650 |
|
7 |
|a Deus.
|2 local.
|
| 650 |
|
7 |
|a Gas Cooled Reactors.
|2 local.
|
| 650 |
|
7 |
|a Specific Nuclear Reactors And Associated Plants.
|2 edbsc.
|
| 710 |
2 |
|
|a Alabama A & M University.
|4 res.
|
| 710 |
1 |
|
|a United States.
|b Department of Energy.
|b Office of Scientific and Technical Information.
|4 dst.
|
| 856 |
4 |
0 |
|u http://www.osti.gov/servlets/purl/5061063/
|z Online Access
|
| 907 |
|
|
|a .b77092053
|b 03-07-23
|c 04-22-14
|
| 998 |
|
|
|a web
|b 04-22-14
|c f
|d m
|e p
|f eng
|g alu
|h 0
|i 1
|
| 956 |
|
|
|a Information bridge
|
| 999 |
f |
f |
|i 88d354d7-5eba-5001-8584-27336489ff4d
|s 138c7ade-a111-52d6-9f23-a90ea9d847eb
|
| 952 |
f |
f |
|p Can circulate
|a University of Colorado Boulder
|b Online
|c Online
|d Online
|e E 1.99: conf-820915-2
|h Superintendent of Documents classification
|i web
|n 1
|
