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|a (TOE)ost6403642
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|a (TOE)6403642
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|a TOE
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|a E 1.99:conf-830304-16
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|a E 1.99:conf-830304-16
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|a Nodal method for three-dimensional fast-reactor calculations in hexagonal geometry. [LMFBR]
|h [electronic resource]
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| 260 |
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|a Argonne, Ill. :
|b Argonne National Lab ;
|a Oak Ridge, Tenn. :
|b distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy,
|c 1983.
|
| 300 |
|
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|a Pages: 16 :
|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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| 500 |
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|a Published through the Information Bridge: DOE Scientific and Technical Information.
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| 500 |
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|a 01/01/1983.
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| 500 |
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|a "conf-830304-16"
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| 500 |
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|a "DE83008875"
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| 500 |
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|a American Nuclear Society topical conference on computational methods, Salt Lake City, UT, USA, 28 Mar 1983.
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| 500 |
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|a Lawrence, R.D.
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| 520 |
3 |
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|a A nodal method is developed for the solution of the multigroup neutron-diffusion equation in three-dimensional hexagonal-z geometry. The method employs an extension to hexagonal geometry of the transverse-integration procedure used extensively in the development of nodal schemes in Cartesian geometry. The partially-integrated fluxes in the three hex-plane directions are approximated by a polynomial tailored to the unique properties of the transverse-integrated equations in hexagonal geometry. The final equations, which are cast in the form of local inhomogeneous response matrix equations for each energy group, involve spatial moments of the node-interior flux distribution plus surface-averaged partial currents across the faces of the node.
|
| 536 |
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|b W-31-109-ENG-38.
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| 650 |
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7 |
|a Kinetics.
|2 local.
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| 650 |
|
7 |
|a Breeder Reactors.
|2 local.
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| 650 |
|
7 |
|a Transport Theory.
|2 local.
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| 650 |
|
7 |
|a Epithermal Reactors.
|2 local.
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| 650 |
|
7 |
|a Reactors.
|2 local.
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| 650 |
|
7 |
|a Multigroup Theory.
|2 local.
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| 650 |
|
7 |
|a Liquid Metal Cooled Reactors.
|2 local.
|
| 650 |
|
7 |
|a Lmfbr Type Reactors.
|2 local.
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| 650 |
|
7 |
|a Neutron Flux.
|2 local.
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| 650 |
|
7 |
|a Neutron Transport Theory.
|2 local.
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| 650 |
|
7 |
|a Fbr Type Reactors.
|2 local.
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| 650 |
|
7 |
|a Reactor Cores.
|2 local.
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| 650 |
|
7 |
|a Fast Reactors.
|2 local.
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| 650 |
|
7 |
|a Three-dimensional Calculations.
|2 local.
|
| 650 |
|
7 |
|a Reactor Components.
|2 local.
|
| 650 |
|
7 |
|a Radiation Flux.
|2 local.
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| 650 |
|
7 |
|a Reactor Kinetics.
|2 local.
|
| 650 |
|
7 |
|a Specific Nuclear Reactors And Associated Plants.
|2 edbsc.
|
| 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 |
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|u http://www.osti.gov/servlets/purl/6403642-ydyqqp/
|z Online Access
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| 907 |
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|a .b60010083
|b 03-06-23
|c 05-30-10
|
| 998 |
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|a web
|b 05-30-10
|c f
|d m
|e p
|f eng
|g ilu
|h 0
|i 1
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| 956 |
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|a Information bridge
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|s cd4960bf-f82d-56c6-95a3-b8b086df7eb8
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| 952 |
f |
f |
|p Can circulate
|a University of Colorado Boulder
|b Online
|c Online
|d Online
|e E 1.99:conf-830304-16
|h Superintendent of Documents classification
|i web
|n 1
|
