These classes represent information specific to one case and concern the description of geometry, composition, moderation, and reflection characteristics, spectra data, benchmark keff and associated uncertainty, and sample calculations.

 

Geometry Description

 

The geometry of the experiment is described as:

• Core geometry: A description of the overall configuration. Possible choices are: Single Homogeneous Unit, Single Assembly, Array of Clad or Unclad Homogeneous Units, Array of Assemblies, or Complex Geometry.
• Assembly description: In the case of configurations containing assemblies, a description is given of the assembly. Possible choices are: Lattice of Fuel Pins or Tubes, Fuel Plates, or Complex Geometry.
• Basic fuel unit: Finally the elementary fuel unit is described (pincell in the case of an assembly or the entire unit for homogeneous configurations). The list of choices is much larger in this case.

 

In the case of complicated shapes for the core or for the assembly, a summary description is given as a free text.

 

Composition

 

The database contains data for fuel compositions. When a configuration contains multiple fissile units of different compositions, all these compositions were entered when judged useful. Some experiments, however, contain several fissile media that differ only slightly. Only a typical or average value is provided in the database. For example, multiple fuel compositions are used in each configuration given in HEU-COMP-INTER-003, but only a typical value is entered into the database.

 

The data entered into the database is atom densities in atoms/(barn-cm) as given in Section 3.3 of the evaluation. This data, however, is not displayed in a summary. It is used to compute the uranium and plutonium isotopic vectors in weight percents. The atom densities are also used to compute the moderator-to-fuel and the moderator-to-fissile density ratios for homogeneous fuels.

 

Moderator-to-fuel ratio

 

Depending upon the fuel configuration, the moderator-to-fuel ratio is calculated as the ratio of atomic densities (homogeneous media) or the ratio of respective volumes (assembly type geometry). For homogeneous media, the moderator-to-fissile atomic densities ratio is also given. For simple cases, the information is automatically calculated from the geometry and composition data. For complex situations, this information was calculated by hand and entered into the database with the mention of the moderation ratio type (atom density or volume ratio...).

 

Configurations containing different fissile units

 

Some experiments contain more than a single type of fissile unit. The difference can be the assembly description (a typical example is reactor experiments with a driver assembly and a test assembly of different pitches), fuel form or composition. For such configurations, the fuel descriptions are entered for the different units and are displayed in the summary. These multiple compositions and geometries are stored as subcases in DICE. A subcase has an evaluation identification number, a case number, and a subcase identifier. For example, MIX-MISC-THERM-001-006a is a subcases and MIX-MISC-THERM-006 is the main case.

 

Package icsbep.metier.cases

 

Package icsbep.metier.cases contains a collection of classes that represent a case retrieved by a SQL request.