You need JavaScript to view this

Three dimensions transport calculations for PWR core; Calcul de coeur R.E.P. en transport 3D

Abstract

The objective of this work is to define improved 3-D core calculation methods based on the transport theory. These methods can be particularly useful and lead to more precise computations in areas of the core where anisotropy and steep flux gradients occur, especially near interface and boundary conditions and in regions of high heterogeneity (bundle with absorbent rods). In order to apply the transport theory a new method for calculating reflector constants has been developed, since traditional methods were only suited for 2-group diffusion core calculations and could not be extrapolated to transport calculations. In this thesis work, the new method for obtaining reflector constants is derived regardless of the number of energy groups and of the operator used. The core calculations results using the reflector constants thereof obtained have been validated on the EDF's power reactor Saint Laurent B1 with MOX loading. The advantages of a 3-D core transport calculation scheme have been highlighted as opposed to diffusion methods; there are a considerable number of significant effects and potential advantages to be gained in rod worth calculations for instance. These preliminary results obtained with on particular cycle will have to be confirmed by more systematic analysis. Accidents like MSLB  More>>
Authors:
Publication Date:
Jul 01, 2000
Product Type:
Technical Report
Report Number:
CEA-R-5935
Reference Number:
EDB-01:052106
Resource Relation:
Other Information: 58 refs; PBD: 2000
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; ALBEDO; CALCULATION METHODS; COMPUTERIZED SIMULATION; NEUTRON REFLECTORS; REACTOR CORES; SAINT LAURENT-B1 REACTOR; THREE-DIMENSIONAL CALCULATIONS; TRANSPORT THEORY; VALIDATION
OSTI ID:
20165231
Research Organizations:
CEA/Saclay, Dept. de Mecanique et de Technologie (DMT), 91 - Gif-sur-Yvette (France)
Country of Origin:
France
Language:
French
Other Identifying Numbers:
TRN: FR0104555025218
Availability:
Available from INIS in electronic form
Submitting Site:
FRN
Size:
285 pages
Announcement Date:

Citation Formats

Richebois, E. Three dimensions transport calculations for PWR core; Calcul de coeur R.E.P. en transport 3D. France: N. p., 2000. Web.
Richebois, E. Three dimensions transport calculations for PWR core; Calcul de coeur R.E.P. en transport 3D. France.
Richebois, E. 2000. "Three dimensions transport calculations for PWR core; Calcul de coeur R.E.P. en transport 3D." France.
@misc{etde_20165231,
title = {Three dimensions transport calculations for PWR core; Calcul de coeur R.E.P. en transport 3D}
author = {Richebois, E}
abstractNote = {The objective of this work is to define improved 3-D core calculation methods based on the transport theory. These methods can be particularly useful and lead to more precise computations in areas of the core where anisotropy and steep flux gradients occur, especially near interface and boundary conditions and in regions of high heterogeneity (bundle with absorbent rods). In order to apply the transport theory a new method for calculating reflector constants has been developed, since traditional methods were only suited for 2-group diffusion core calculations and could not be extrapolated to transport calculations. In this thesis work, the new method for obtaining reflector constants is derived regardless of the number of energy groups and of the operator used. The core calculations results using the reflector constants thereof obtained have been validated on the EDF's power reactor Saint Laurent B1 with MOX loading. The advantages of a 3-D core transport calculation scheme have been highlighted as opposed to diffusion methods; there are a considerable number of significant effects and potential advantages to be gained in rod worth calculations for instance. These preliminary results obtained with on particular cycle will have to be confirmed by more systematic analysis. Accidents like MSLB (main steam line break) and LOCA (loss of coolant accident) should also be investigated and constitute challenging situations where anisotropy is high and/or flux gradients are steep. This method is now being validated for others EDF's PWRs' reactors, as well as for experimental reactors and other types of commercial reactors. (author)}
place = {France}
year = {2000}
month = {Jul}
}