An assessment of finite element synthesis model using 3D FEM
Creators
- 1. Theoretical Physics Div., Bhabha Atomic Res. Centre, 5th floor, Central Complex, Bombay
Description
For the solution of multigroup diffusion theory equations a code system called FEMSYN has been developed. The code FEMSYN incorporates a finite difference (FD) module, a finite element (FE) module and one module based on single channel flux synthesis (SCFS) method, which uses trial functions generated by either FD or FE method. The 3D problems can be tackled by all the three modules. The 3D FE solutions are cheaper in comparison with fine mesh FD computations and are quite accurate. The accuracy is improved by proper choice of rectangular and triangular right prismatic elements and polynomial order in case of 3D FE analyses. Synthesis method using FE trial functions provides the fastest means of solution for 3D problems. In this paper, the FE synthesis method has been compared with 3D FE technique for the case of IAEA PWR benchmark problem. It is concluded from the above comparison that FE synthesis method can give at negligible computational efforts, accurate eigenvalue estimates and satisfactory prediction of reactor core power profiles
Additional details
Publishing Information
- Publisher
- American Nuclear Society.
- Imprint Place
- LaGrange Park, IL (USA)
- ISBN
- 0-919784-02-X
- Imprint Title
- Proceedings of the international conference on numerical methods in nuclear engineering. Volume 1
- Journal Page Range
- p. 249-268.
Conference
- Title
- International conference on numerical methods in nuclear engineering.
- Dates
- 6-9 Sep 1983.
- Place
- Montreal (Canada).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 17051522
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCURACY; COMPUTER CALCULATIONS; EIGENVALUES; F CODES; FINITE DIFFERENCE METHOD; FINITE ELEMENT METHOD; NEUTRON DIFFUSION EQUATION; NEUTRON TRANSPORT; NEUTRON TRANSPORT THEORY; REACTOR CORES
- Descriptors DEC
- COMPUTER CODES; ITERATIVE METHODS; NEUTRAL-PARTICLE TRANSPORT; NUMERICAL SOLUTION; RADIATION TRANSPORT; REACTOR COMPONENTS; TRANSPORT THEORY