Neutron transport analysis for nuclear reactor design

Title: Neutron transport analysis for nuclear reactor design

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Abstract

Replacing regular mesh-dependent ray tracing modules in a collision/transfer probability (CTP) code with a ray tracing module based upon combinatorial geometry of a modified geometrical module (GMC) provides a general geometry transfer theory code in two dimensions (2D) for analyzing nuclear reactor design and control. The primary modification of the GMC module involves generation of a fixed inner frame and a rotating outer frame, where the inner frame contains all reactor regions of interest, e.g., part of a reactor assembly, an assembly, or several assemblies, and the outer frame, with a set of parallel equidistant rays (lines) attached to it, rotates around the inner frame. The modified GMC module allows for determining for each parallel ray (line), the intersections with zone boundaries, the path length between the intersections, the total number of zones on a track, the zone and medium numbers, and the intersections with the outer surface, which parameters may be used in the CTP code to calculate collision/transfer probability and cross-section values.

Inventors:

Vujic, Jasmina L ^[1]

Lisle, IL

Publication Date:: 1993-01-01

Research Org.:: Argonne National Lab. (ANL), Argonne, IL (United States)

OSTI Identifier:: 869045

Patent Number(s):: US 5267276

Assignee:: University of Chicago (Chicago, IL)

DOE Contract Number:: W-31109-ENG-38

Resource Type:: Patent

Country of Publication:: United States

Language:: English

Subject:: neutron; transport; analysis; nuclear; reactor; design; replacing; regular; mesh-dependent; ray; tracing; modules; collision; transfer; probability; ctp; code; module; based; combinatorial; geometry; modified; geometrical; gmc; provides; theory; dimensions; 2d; analyzing; control; primary; modification; involves; generation; fixed; inner; frame; rotating; outer; contains; regions; assembly; assemblies; set; parallel; equidistant; rays; lines; attached; rotates; allows; determining; line; intersections; zone; boundaries; path; length; total; zones; track; medium; surface; parameters; calculate; cross-section; values; reactor design; path length; nuclear reactor; outer surface; reactor assembly; ray tracing; outer frame; tracing module; /376/

Citation Formats


                    Vujic, Jasmina L. Neutron transport analysis for nuclear reactor design.  United States: N. p., 1993. 
        Web.

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                    Vujic, Jasmina L. Neutron transport analysis for nuclear reactor design.  United States.

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                    Vujic, Jasmina L. Fri .  
        "Neutron transport analysis for nuclear reactor design".  United States.  https://www.osti.gov/servlets/purl/869045.

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@article{osti_869045,

  title        = {Neutron transport analysis for nuclear reactor design},

  author       = {Vujic, Jasmina L},

  abstractNote = {Replacing regular mesh-dependent ray tracing modules in a collision/transfer probability (CTP) code with a ray tracing module based upon combinatorial geometry of a modified geometrical module (GMC) provides a general geometry transfer theory code in two dimensions (2D) for analyzing nuclear reactor design and control. The primary modification of the GMC module involves generation of a fixed inner frame and a rotating outer frame, where the inner frame contains all reactor regions of interest, e.g., part of a reactor assembly, an assembly, or several assemblies, and the outer frame, with a set of parallel equidistant rays (lines) attached to it, rotates around the inner frame. The modified GMC module allows for determining for each parallel ray (line), the intersections with zone boundaries, the path length between the intersections, the total number of zones on a track, the zone and medium numbers, and the intersections with the outer surface, which parameters may be used in the CTP code to calculate collision/transfer probability and cross-section values.},

  doi          = {},

  url          = {https://www.osti.gov/biblio/869045},
  journal      = {},
number       = ,

  volume       = ,

  place        = {United States},

  year         = {1993},

  month        = {1}

}

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