Development of advanced nodal methods for hexagonal geometry reactors
It is proposed to develop a multigroup, three-dimensional nodal neutron diffusion method for hexagonal geometry reactors. The proposed method differs from all existing hexagonal nodal diffusion methods by its use of net currents rather than partial currents and differs from all but one by its use of a local analytical solution rather than a polynomial approach. These two differences are expected to yield a faster, more accurate method that is easily vectorizable and concurrency capable. The method will treat feedback and depletion induced homogeneities explicitly via in-node variable cross sections. It will also incorporate discontinuity factors and thermal hydraulic feedback via coupling to a newly developed semi-analytical thermal-hydraulic code. The use of a tight coupling algorithm will allow the method to treat transients very efficiently. The research will also include the development of a hexagonal geometry, burnup-corrected, depletion method. The issue of compatibility of the variable cross section methods (and of kinetic feedback) with current formulations of the equivalence theory will be addressed and a resolution of the issue sought.
- Research Organization:
- Illinois Univ., Urbana, IL (USA). Dept. of Nuclear Engineering
- Sponsoring Organization:
- USDOE; USDOE, Washington, DC (USA)
- DOE Contract Number:
- FG07-90ER13025
- OSTI ID:
- 5626236
- Report Number(s):
- DOE/ER/13025-1; ON: DE91013703; TRN: 91-019022
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
NEUTRON DIFFUSION EQUATION
NODAL EXPANSION METHOD
REACTORS
FEEDBACK
HEAT TRANSFER
HEXAGONAL CONFIGURATION
HYDRAULICS
PROGRESS REPORT
THREE-DIMENSIONAL CALCULATIONS
CONFIGURATION
DIFFERENTIAL EQUATIONS
DOCUMENT TYPES
ENERGY TRANSFER
EQUATIONS
FLUID MECHANICS
MECHANICS
220100* - Nuclear Reactor Technology- Theory & Calculation
990200 - Mathematics & Computers