A complementary Doppler Broadening formalism and its impact on nuclear reactor simulation
Creators
- 1. Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Inst. fuer Neutronenphysik und Reaktortechnik
- 2. Rensselaer Polytechnic Inst., Troy, NY (United States). Dept. of Mechanical, Aerospace, and Nuclear Engineering
Description
The Boltzmann Transport equation is the governing formalism upon which simulations of nuclear reactors are performed, in particular when strong absorption or anisotropic scattering are significant. On the left (loss) hand side of the balance equation one finds the absorption and the scattering cross section Σa(E'), Σs(E') respectively. Those cross sections are energy and temperature dependent i.e. Doppler Broadened. The scattering cross section appears explicitly again on the right (production) hand side of the equation in its differential form ∫∫0∞Σ(E → E'; Ω → Ω')dE dΩ. However, this term is commonly evaluated at 0 K and it does not account for the existing resonances which are the underlying characteristic for Doppler Broadening. Evidently one gets an inherent inconsistency between the integral and differential scattering cross section within the transport solver codes. In this study this missing Doppler Broadened formalism for the differential scattering cross section is introduced in its stochastic and deterministic form. The impact on core criticality is shown to be up to 600 pcm and the change in the nuclides' inventory significant, in particular the 239PU content can be changed by several percents. (orig.)
Additional details
Publishing Information
- Journal Title
- Kerntechnik (1987)
- Journal Volume
- 76
- Journal Issue
- 3
- Journal Page Range
- p. 185-189
- ISSN
- 0932-3902
- CODEN
- KERNEU
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 42080439
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- ABSORPTION; ANISOTROPY; BOLTZMANN EQUATION; BURNUP; COMPUTERIZED SIMULATION; CRITICALITY; DIFFERENTIAL CROSS SECTIONS; DOPPLER BROADENING; EV RANGE 01-10; INTEGRAL CROSS SECTIONS; KERNELS; NEUTRON REACTIONS; NEUTRON TRANSPORT THEORY; PLUTONIUM 239; PLUTONIUM 241; PWR TYPE REACTORS; REACTOR CORES; RESONANCE SCATTERING; STOCHASTIC PROCESSES; TEMPERATURE DEPENDENCE; TEMPERATURE RANGE 0273-0400 K; TEMPERATURE RANGE 0400-1000 K; TEMPERATURE RANGE 1000-4000 K; URANIUM 235; URANIUM 238 TARGET
- Descriptors DEC
- ACTINIDE NUCLEI; ALPHA DECAY RADIOISOTOPES; BARYON REACTIONS; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CROSS SECTIONS; DIFFERENTIAL EQUATIONS; ENERGY RANGE; ENRICHED URANIUM REACTORS; EQUATIONS; EV RANGE; EVEN-ODD NUCLEI; HADRON REACTIONS; HEAVY NUCLEI; INELASTIC SCATTERING; INTEGRO-DIFFERENTIAL EQUATIONS; INTERNAL CONVERSION RADIOISOTOPES; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; KINETIC EQUATIONS; LINE BROADENING; MINUTES LIVING RADIOISOTOPES; NUCLEAR REACTIONS; NUCLEI; NUCLEON REACTIONS; PARTIAL DIFFERENTIAL EQUATIONS; PLUTONIUM ISOTOPES; POWER REACTORS; RADIOISOTOPES; REACTOR COMPONENTS; REACTORS; SCATTERING; SIMULATION; SORPTION; SPONTANEOUS FISSION RADIOISOTOPES; TARGETS; TEMPERATURE RANGE; THERMAL REACTORS; TRANSPORT THEORY; URANIUM ISOTOPES; WATER COOLED REACTORS; WATER MODERATED REACTORS; YEARS LIVING RADIOISOTOPES