This book provides an overview of the IMS Database Recovery Control; facility ( DBRC) and also discusses the administrative and operational. This section contains a description of the DBRC commands. Use these commands to add to, change, and delete information in the RECON and to generate the. DBRC Commands. This chapter contains a description of the DBRC commands. Use these commands to add to, change, and delete information in the.

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The method was developed especially for the purpose of multi-physics coupling see belowwhere it can be used for modeling a wide variation of material temperatures or even continous temperature distributions. The results can be divided into an arbitrary number of energy and time bins. We have also created standard data analysis queries to allow users to manipulate and understand the data more easily. The source distribution for photon transport simulations can be obtained from a radioactive decay source.
The values can also be obtained from a Monte Carlo based volume calculation routine or entered manually.

October 13, M. The model works nad several levels particles inside a pebble and pebbles inside the core and it has been tested in realistic double-heterogeneous reactor configurations consisting of over 60 million randomly positioned units Suikkanen, ; Rintala, The computational overhead from handling the unstructured configuration is moderate compared to a similar regular-lattice model.
2.1 DBRC Commands.
When the third RECON data set starts to be used, the remaining valid data set is copied to the spare. Secondary photons are produced by atomic relaxation and bremsstrahlung, handled using the thick-target bremsstrahlung TTB approximation.
It contains the current information. In addition to discrepancies in the transport simulation, there are additional factors related to decay, fission yield and isomeric branching ratio data, formulation of transmutation and decay chains, depletion algorithms, and so on.
The main features and capabilities of the code are introduced below. Isomeric branching ratios for neutron reactions are not included reffrence the ACE format data libraries.
“DBRC Guide and Reference” IBM Library Server
The spatial integration domain can be defined by a combination of cells, universes, lattices and materials, or using a three-dimensional super-imposed mesh. Results and output Spatial homogenization was the main intended application for Serpent when the project was started in Coupled multi-physics simulations Two-way coupling to thermal hydraulics, CFD and fuel performance codes has been a major topic in Serpent development for the past several years.
Reaction rates are normalized to total power, specific power density, flux, fission or source rate, and the normalization can be changed by dividing the irradiation cycle into a number of separate depletion intervals.
Serpent 1 base version: Interaction physics Serpent reads continuous-energy cross sections from ACE format data refeernce. November 28 The first method is the Transmutation Trajectory Analysis TTA method Cetnar,based on the analytical solution of linearized depletion chains. Transport cross sections and diffusion coefficients calculated ahd several methods. It will take only 2 minutes to fill in.
File System Forensic Analysis. Please tell us what format you need. Energy, 82 The grid size may become prohibitively large in burnup calculations, often involving more than actinide and fission dbfc nuclides.
In this source mode Serpent combines the compositions of activated materials into photon emission spectra read from ENDF format radioactive decay data files. The recommended publication for referencing Serpent is: The irradiation history is defined in units of time or burnup. This class of records includes: Doppler-broadening of cross sections A built-in Doppler-broadening preprocessor routine Viitanen, allows adjusting the temperatures anv ACE format cross sections. Serpent has the capability to import CAD and unstructured mesh based geometries as part of the universe structure.
The best way to validate the Monte Carlo based code sequence is to compare the results to reference Serpent full-core calculations. The use of a single energy grid results in a major speed-up in calculation, as the number of CPU time consuming grid search iterations is reduced to minimum. Request an accessible format. Effective multiplication factors and homogenized few-group reaction cross sections are within the statistical accuracy from the reference results, when the same ACE libraries are used in the calculations.
May 19, Ville Valtavirta defended his Doctoral Thesis: Flux-volume-averaged one-group transmutation cross sections are calculated either during the transport simulation, or by collapsing the continuous-energy reaction cross sections after the calculation has been completed using a flux spectrum collected on the unionized energy grid.
Download organisation level data MS Excel Spreadsheet5. As a general rule, more than one set of RECON data sets is necessary if all the following anr are true: If this name does not match, DBRC treats this database as if it was not registered. This is important especially for theses, which are otherwise difficult to keep track of. Fission product poisons Xe and Sm can be handled separately from the other nuclides, and iterated to their equilibrium concentration during the transport simulation.
The third data set the spare is used in the following cases: The transient capability in Serpent allows the modeling of both prompt super-critical reactivity excursions and slow transients below prompt criticality. The applications can be roughly divided into three categories:
