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|a (TOE)ost5193964
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|a (TOE)5193964
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|a TOE
|c TOE
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|a GDWR
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|a 22
|2 edbsc
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|a E 1.99:ornl/tm-7305
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|a E 1.99:ornl/tm-7305
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|a ornl/tm-7305
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|a Development, implementation, and verification of multicycle depletion perturbation theory for reactor burnup analysis
|h [electronic resource]
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| 260 |
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|a Oak Ridge, Tenn. :
|b Oak Ridge National Laboratory. ;
|a Oak Ridge, Tenn. :
|b distributed by the Office of Scientific and Technical Information, U.S. Department of Energy,
|c 1980.
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| 300 |
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|a Pages: 179 :
|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 SciTech Connect.
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| 500 |
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|a 08/01/1980.
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| 500 |
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|a "ornl/tm-7305"
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| 500 |
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|a White, J.R.
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|a A generalized depletion perturbation formulation based on the quasi-static method for solving realistic multicycle reactor depletion problems is developed and implemented within the VENTURE/BURNER modular code system. The present development extends the original formulation derived by M.L. Williams to include nuclide discontinuities such as fuel shuffling and discharge. This theory is first described in detail with particular emphasis given to the similarity of the forward and adjoint quasi-static burnup equations. The specific algorithm and computational methods utilized to solve the adjoint problem within the newly developed DEPTH (Depletion Perturbation Theory) module are then briefly discussed. Finally, the main features and computational accuracy of this new method are illustrated through its application to several representative reactor depletion problems.
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| 536 |
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|b W-7405-ENG-26.
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| 650 |
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7 |
|a Bwr Type Reactors.
|2 local.
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| 650 |
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|a Fuel Cycle.
|2 local.
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| 650 |
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|a Reactor Cores.
|2 local.
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| 650 |
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|a Perturbation Theory.
|2 local.
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| 650 |
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|a Nuclear Power Plants.
|2 local.
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| 650 |
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|a Pwr Type Reactors.
|2 local.
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| 650 |
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7 |
|a Burnup.
|2 local.
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| 650 |
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7 |
|a Computer Calculations.
|2 local.
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| 650 |
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7 |
|a Fuel Management.
|2 local.
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| 650 |
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|a Reactor Kinetics.
|2 local.
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| 650 |
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|a Kinetics.
|2 local.
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| 650 |
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|a Nuclear Facilities.
|2 local.
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| 650 |
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|a Power Plants.
|2 local.
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| 650 |
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|a Reactor Components.
|2 local.
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| 650 |
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|a Reactors.
|2 local.
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| 650 |
|
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|a Thermal Power Plants.
|2 local.
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| 650 |
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|a Water Cooled Reactors.
|2 local.
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| 650 |
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|a Water Moderated Reactors.
|2 local.
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| 650 |
|
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|a General Studies Of Nuclear Reactors.
|2 edbsc.
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| 710 |
2 |
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|a Oak Ridge National Laboratory.
|4 res.
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| 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 |
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|u http://www.osti.gov/scitech/biblio/5193964
|z Online Access (via OSTI)
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| 907 |
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|a .b9053461x
|b 03-09-23
|c 02-15-17
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| 998 |
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|a web
|b 02-15-17
|c f
|d m
|e p
|f eng
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|h 0
|i 1
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| 956 |
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|a Information bridge
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|i 80cecc77-6a79-50cb-9f68-ffa5dc7ff236
|s f09aabbe-c806-5dec-b850-ce9730f7927f
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| 952 |
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|p Can circulate
|a University of Colorado Boulder
|b Online
|c Online
|d Online
|e E 1.99:ornl/tm-7305
|h Superintendent of Documents classification
|i web
|n 1
|
