Evaluation of history effects in full-core calculations
Result description
Thanks to the rapid development of the computing power it is nowadays feasible to generate macroscopic data libraries for each computing node with its particular depletion history. The method is based on coupling the core physics code (ANDREA, which is aNEM-based 2-group diffusion code for VVER reactors) and the lattice code (HELIOS 2) in an iterative scheme. Each core physics code run establishes an estimate of the depletion history in terms of local parameter values (that is, values related to each of 7000 nodes of core discretization) depending on the local burnup; nodes with the same fuel composition and similar burnup history are grouped and then for each of the 700 "mutually different" nodes a new run of lattice code is performed, generating a new node-specific data library for the macrocode. The iterations are repeated until the power distribution has converged; however, usually only two iterations are needed due to the fact that also the node-specific libraries are parameteriz
Keywords
nuclear reactorscore physics codesnuclear power plantsmodel uncertaintiespower distribution
The result's identifiers
Result code in IS VaVaI
Result on the web
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DOI - Digital Object Identifier
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Alternative languages
Result language
angličtina
Original language name
Evaluation of history effects in full-core calculations
Original language description
Thanks to the rapid development of the computing power it is nowadays feasible to generate macroscopic data libraries for each computing node with its particular depletion history. The method is based on coupling the core physics code (ANDREA, which is aNEM-based 2-group diffusion code for VVER reactors) and the lattice code (HELIOS 2) in an iterative scheme. Each core physics code run establishes an estimate of the depletion history in terms of local parameter values (that is, values related to each of 7000 nodes of core discretization) depending on the local burnup; nodes with the same fuel composition and similar burnup history are grouped and then for each of the 700 "mutually different" nodes a new run of lattice code is performed, generating a new node-specific data library for the macrocode. The iterations are repeated until the power distribution has converged; however, usually only two iterations are needed due to the fact that also the node-specific libraries are parameteriz
Czech name
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Czech description
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Classification
Type
D - Article in proceedings
CEP classification
JF - Nuclear energy
OECD FORD branch
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Result continuities
Project
Continuities
P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)
Others
Publication year
2013
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů
Data specific for result type
Article name in the collection
International Congress on Advances in Nuclear Power Plants (ICAPP 2013) Nuclear Power ? A Safe and Sustainable Choice for Green Future
ISBN
978-1-63266-038-1
ISSN
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e-ISSN
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Number of pages
11
Pages from-to
512-522
Publisher name
Korean Nuclear Society
Place of publication
Daejeon, Korea
Event location
Jeju Island, Korea
Event date
Jan 1, 2013
Type of event by nationality
WRD - Celosvětová akce
UT code for WoS article
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Basic information
Result type
D - Article in proceedings
CEP
JF - Nuclear energy
Year of implementation
2013