|
|
|
|
| LEADER |
00000nam a22000003u 4500 |
| 001 |
b7218166 |
| 003 |
CoU |
| 005 |
20160624231723.3 |
| 006 |
m o d f |
| 007 |
cr ||||||||||| |
| 008 |
160906e19751001||| o| f1|||||eng|d |
| 035 |
|
|
|a (TOE)ost4168939
|
| 035 |
|
|
|a (TOE)4168939
|
| 040 |
|
|
|a TOE
|c TOE
|
| 049 |
|
|
|a GDWR
|
| 072 |
|
7 |
|a 22
|2 edbsc
|
| 086 |
0 |
|
|a E 1.99:conf-751013--9
|
| 086 |
0 |
|
|a E 1.99:conf-751013--9
|
| 088 |
|
|
|a conf-751013--9
|
| 245 |
0 |
0 |
|a Implicit Eulerian method for analyzing transient phenomena in fast reactors
|h [electronic resource]
|
| 260 |
|
|
|a Argonne, Ill. :
|b Argonne National Laboratory ;
|a Oak Ridge, Tenn. :
|b distributed by the Office of Scientific and Technical Information, U.S. Department of Energy,
|c 1975.
|
| 300 |
|
|
|a Pages: 12 :
|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 10/01/1975.
|
| 500 |
|
|
|a "conf-751013--9"
|
| 500 |
|
|
|a 12. annual meeting of the Society of Engineering Science, Austin, Texas, USA, 21 Oct 1975.
|
| 500 |
|
|
|a Wang, C.Y.
|
| 520 |
3 |
|
|a An Eulerian compressible hydrodynamic method is presented for analyzing transient phenomena in nuclear reactors following hypothetical excursions. The method uses the implicit integration scheme to solve nonlinear equations of fluid dynamics in conjunction with a thin-shell analysis to calculate the response of the wall boundary. Detailed formulations are given. Results are presented for two example problems and compared with available experimental data. 6 references. (auth)
|
| 536 |
|
|
|b W-31-109-ENG-38.
|
| 650 |
|
7 |
|a *Lmfbr Type Reactors-- Reactor Safety.
|2 local.
|
| 650 |
|
7 |
|a *Reactor Core Disruption-- Pressure Gradients.
|2 local.
|
| 650 |
|
7 |
|a Bubbles.
|2 local.
|
| 650 |
|
7 |
|a Excursions.
|2 local.
|
| 650 |
|
7 |
|a Hydrodynamics.
|2 local.
|
| 650 |
|
7 |
|a Liquid Flow.
|2 local.
|
| 650 |
|
7 |
|a N77900* --Reactors--Reactor Safety & Environmental Aspects.
|2 edbsc.
|
| 650 |
|
7 |
|a N77500 --Reactors--Power Reactors, Breeding.
|2 edbsc.
|
| 650 |
|
7 |
|a 0900* --Nuclear Reactor Technology--Reactor Safety.
|2 edbsc.
|
| 710 |
2 |
|
|a Argonne National Laboratory.
|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/scitech/biblio/4168939
|z Online Access
|
| 907 |
|
|
|a .b72181667
|b 03-07-23
|c 11-08-12
|
| 998 |
|
|
|a web
|b 09-09-16
|c f
|d m
|e p
|f eng
|g
|h 0
|i 2
|
| 956 |
|
|
|a Information bridge
|
| 999 |
f |
f |
|i 66398928-acac-59bd-944d-98905c7d6f31
|s 5714718e-3a63-57a6-91f3-5a03943cbb40
|
| 952 |
f |
f |
|p Can circulate
|a University of Colorado Boulder
|b Online
|c Online
|d Online
|e E 1.99:conf-751013--9
|h Superintendent of Documents classification
|i web
|n 1
|
