Modul data base for calculation of average neutron phisics characteristics of the WWER type reactor cell in the area [4.65 keV - 0.46 eV]
Creators
- 1. Bylgarska Akademiya na Naukite, Sofia (Bulgaria). Inst. za Yadrena Izsledvaniya i Yadrena Energetika
Description
Part of a modul system, calculating neutron-physical characteristics of the reactor cell in the resonance area 4.56 keV-0.465 keV is presented. A physical model of the NESSEL-4 programme is used. The calculation of neutron-physical characteristics has three stages: 1) solution of equation of neutron transport in unlimited lattice of equal thermal cells or in a cell of this lattice; 2) the energy spectra of neutron current neutron flux; 3) the calculation of neutron physical characteristics of the elemental areas of the cell; microscope macrogroups cross sections of elements of the cell influencing the neutron energy spectra in it; neutron-physical characteristics of homogenious cell; resonance integrals of resonance elements. 10 independent programme moduls are created taking into account the influence of the neutron loss throughout the boundary of the final heterogenic lattice on the neutron spectra. With the purpose to verify the modul system FRAM with the data base a calculation of neutron physical characteristics of new thermal cell of the reactor YANKEE has been made. The results are compared with that of NESSEL-4. The divergences are analyzed and three mistakes in the programme NESSEL-4 are found. 1 tab., 7 refs
Additional details
Publishing Information
- Journal Title
- Comptes Rendus de l'Academie Bulgare des Sciences
- Journal Volume
- 41
- Journal Issue
- 5
- Series
- C. R. Acad. Bulg. Sci.
- Journal Page Range
- 59-62
- ISSN
- 0366-8681
- CODEN
- CRABA
INIS
- Country of Publication
- Bulgaria
- Country of Input or Organization
- Bulgaria
- INIS RN
- 22069536
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPUTER CODES; ERRORS; EV RANGE; FLUX DENSITY; GROUP CONSTANTS; HOMOGENIZATION METHODS; KEV RANGE; MEV RANGE; NEUTRON FLUX; NEUTRON SPECTRA; NEUTRON TRANSFER; REACTOR CELLS; REACTOR CORES; RESONANCE INTEGRALS; WWER TYPE REACTORS
- Descriptors DEC
- CROSS SECTIONS; ENERGY RANGE; ENRICHED URANIUM REACTORS; INTEGRALS; POWER REACTORS; PWR TYPE REACTORS; RADIATION FLUX; REACTOR COMPONENTS; REACTORS; SPECTRA; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS