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150804e19790101||| o| f1|||||eng|d |
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|a (TOE)ost5745635
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|a (TOE)5745635
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|a TOE
|c TOE
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|a GDWR
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|a 21
|2 edbsc
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|a 36
|2 edbsc
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|a E 1.99:conf-790884-2
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|a E 1.99:conf-790884-2
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|a conf-790884-2
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|a Development of LIFE4-CN
|h [electronic resource] :
|b a combined code for steady-state and transient analyses of advanced LMFBR fuels.
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260 |
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|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 1979.
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300 |
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|a Pages: 28 :
|b digital, PDF file.
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336 |
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|a text
|b txt
|2 rdacontent.
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337 |
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|a computer
|b c
|2 rdamedia.
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338 |
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|a online resource
|b cr
|2 rdacarrier.
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|a Published through SciTech Connect.
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|a 01/01/1979.
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|a "conf-790884-2"
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|a Post-SMiRT5 second international seminar on mathematical/mechanical modeling of reactor fuel elements, Berlin, F.R. Germany, 20 Aug 1979.
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|a Billone, M.C.; Roth, T.; Liu, Y.Y.; Nayak, U.P.; Zawadzki, S.
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|a The methodology used to develop the LMFBR carbide/nitride fuels code, LIFE4-CN, is described in detail along with some subtleties encountered in code development. Fuel primary and steady-state thermal creep have been used as an example to illustrate the need for physical modeling and the need to recognize the importance of the materials characteristics. A self-consistent strategy for LIFE4-CN verification against irradiation data has been outlined with emphasis on the establishment of the gross uncertainty bands. These gross uncertainty bands can be used as an objective measure to gauge the overall success of the code predictions. Preliminary code predictions for sample steady-state and transient cases are given.
|
536 |
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|b W-31-109-ENG-38.
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650 |
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7 |
|a Computer Codes.
|2 local.
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650 |
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7 |
|a L Codes.
|2 local.
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650 |
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7 |
|a Lmfbr Type Reactors.
|2 local.
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650 |
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7 |
|a Reactor Materials.
|2 local.
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650 |
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7 |
|a Physical Radiation Effects.
|2 local.
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650 |
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7 |
|a Creep.
|2 local.
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650 |
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7 |
|a Nuclear Fuels.
|2 local.
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650 |
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7 |
|a Performance.
|2 local.
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650 |
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7 |
|a Plutonium Carbides.
|2 local.
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650 |
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7 |
|a Plutonium Nitrides.
|2 local.
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650 |
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7 |
|a Thermal Stresses.
|2 local.
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650 |
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7 |
|a Uranium Carbides.
|2 local.
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650 |
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7 |
|a Uranium Nitrides.
|2 local.
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650 |
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7 |
|a Actinide Compounds.
|2 local.
|
650 |
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7 |
|a Breeder Reactors.
|2 local.
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650 |
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7 |
|a Carbides.
|2 local.
|
650 |
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7 |
|a Carbon Compounds.
|2 local.
|
650 |
|
7 |
|a Energy Sources.
|2 local.
|
650 |
|
7 |
|a Epithermal Reactors.
|2 local.
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650 |
|
7 |
|a Fast Reactors.
|2 local.
|
650 |
|
7 |
|a Fbr Type Reactors.
|2 local.
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650 |
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7 |
|a Fuels.
|2 local.
|
650 |
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7 |
|a Liquid Metal Cooled Reactors.
|2 local.
|
650 |
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7 |
|a Mechanical Properties.
|2 local.
|
650 |
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7 |
|a Nitrides.
|2 local.
|
650 |
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7 |
|a Nitrogen Compounds.
|2 local.
|
650 |
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7 |
|a Plutonium Compounds.
|2 local.
|
650 |
|
7 |
|a Pnictides.
|2 local.
|
650 |
|
7 |
|a Radiation Effects.
|2 local.
|
650 |
|
7 |
|a Reactors.
|2 local.
|
650 |
|
7 |
|a Stresses.
|2 local.
|
650 |
|
7 |
|a Transuranium Compounds.
|2 local.
|
650 |
|
7 |
|a Uranium Compounds.
|2 local.
|
650 |
|
7 |
|a Specific Nuclear Reactors And Associated Plants.
|2 edbsc.
|
650 |
|
7 |
|a Materials Science.
|2 edbsc.
|
700 |
1 |
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|a Billone, M.C.
|4 aut.
|
700 |
1 |
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|a Roth, T.
|4 aut.
|
700 |
1 |
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|a Liu, Y.Y.
|4 aut.
|
700 |
1 |
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|a Nayak, U.P.
|4 aut.
|
700 |
1 |
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|a Zawadzki, S.
|4 aut.
|
710 |
2 |
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|a Argonne National Laboratory.
|4 res.
|
710 |
1 |
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|a United States.
|b Department of Energy.
|b Office of Scientific and Technical Information.
|4 dst.
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856 |
4 |
0 |
|u http://www.osti.gov/servlets/purl/5745635/
|z Online Access
|
907 |
|
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|a .b72117783
|b 03-07-23
|c 11-08-12
|
998 |
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|a web
|b 08-04-15
|c f
|d m
|e p
|f eng
|g
|h 0
|i 2
|
956 |
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|a Information bridge
|
999 |
f |
f |
|i 13f6acab-57dc-5efa-85bd-79c94bd1f426
|s 6f3c51fa-0f5f-52c2-ae24-73bdb0108b2a
|
952 |
f |
f |
|p Can circulate
|a University of Colorado Boulder
|b Online
|c Online
|d Online
|e E 1.99:conf-790884-2
|h Superintendent of Documents classification
|i web
|n 1
|