Published March 1993
| Version v1
Miscellaneous
On the calculation of the flux fine distribution in PWR fuel assemblies by the response matrix method
Description
We develop a procedure for the pin wise group flux distribution calculation in a typical PWR fuel assembly, based on the response matrix method. Using a variational procedure and standard perturbation theory as well, we obtain the response matrices for the heterogeneous fuel assembly. A first-order approximation for the perturbed group fluxes is obtained in terms of unperturbed direct and adjoint group fluxes. Two approximation were used: high-order Fourier expansion, and adaptation of Kirchoff's formula. Our method was tested for a PWR fuel assembly with 20 control rods inserted and the results showed that this first-order approach is accurate for the analysed case. (author). 28 refs., 6 figs., 6 tabs
Availability note (English)
Available from the Nuclear Information Center of Brazilian Nuclear Energy Commission, Rio de Janeiro.Additional details
Additional titles
- Original title (Portuguese)
- Sobre o calculo da distribuicao fina de fluxo em elementos combustiveis de reatores PWR por matrizes-resposta
Publishing Information
- Imprint Pagination
- 83 p.
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 28032419
- Subject category
- S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
- Resource subtype / Literary indicator
- Thesis, Non-conventional Literature
- Descriptors DEI
- CRITICALITY; FUEL ASSEMBLIES; FUEL ELEMENTS; NEUTRON FLUX; NEUTRONS; NUCLEAR ENERGY; NUCLEAR ENGINEERING; PWR TYPE REACTORS; REACTOR KINETICS EQUATIONS; RESPONSE MATRIX METHOD
- Descriptors DEC
- BARYONS; CALCULATION METHODS; ELEMENTARY PARTICLES; ENERGY; ENGINEERING; ENRICHED URANIUM REACTORS; EQUATIONS; FERMIONS; HADRONS; NUCLEONS; POWER REACTORS; RADIATION FLUX; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS