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Title: DOS-HEATING6: A general conduction code with nuclear heat generation derived from DOT-IV transport calculations

The HEATING6 heat conduction code is modified to (a) read the multigroup particle fluxes from a two-dimensional DOT-IV neutron- photon transport calculation, (b) interpolate the fluxes from the DOT-IV variable (optional) mesh to the HEATING6 control volume mesh, and (c) fold the interpolated fluxes with kerma factors to obtain a nuclear heating source for the heat conduction equation. The modified HEATING6 is placed as a module in the ORNL discrete ordinates system (DOS), and has been renamed DOS-HEATING6. DOS-HEATING6 provides the capability for determining temperature distributions due to nuclear heating in complex, multi-dimensional systems. All of the original capabilities of HEATING6 are retained for the nuclear heating calculation; e.g., generalized boundary conditions (convective, radiative, finned, fixed temperature or heat flux), temperature and space dependent thermal properties, steady-state or transient analysis, general geometry description, etc. The numerical techniques used in the code are reviewed and the user input instructions and JCL to perform DOS-HEATING6 calculations are presented. Finally a sample problem involving coupled DOT-IV and DOS-HEATING6 calculations of a complex space-reactor configurations described, and the input and output of the calculations are listed. 10 refs., 11 figs., 6 tabs.
Authors:
; ;
Publication Date:
OSTI Identifier:
6928640
Report Number(s):
ORNL/TM-10645
ON: DE88013503
DOE Contract Number:
AC05-84OR21400
Resource Type:
Technical Report
Resource Relation:
Other Information: Portions of this document are illegible in microfiche products
Research Org:
Oak Ridge National Lab., TN (USA); Louisiana State Univ., Baton Rouge (USA)
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE; NUCLEAR POWER PLANTS; DESIGN; RADIATION HEATING; THREE-DIMENSIONAL CALCULATIONS; BUILDING MATERIALS; D CODES; EQUATIONS; GAMMA RADIATION; GAMMA TRANSPORT THEORY; H CODES; KERMA; NEUTRON FLUX; NEUTRON TRANSPORT THEORY; NUMERICAL DATA; ONE-DIMENSIONAL CALCULATIONS; SHIELDING MATERIALS; TEMPERATURE DISTRIBUTION; TWO-DIMENSIONAL CALCULATIONS; COMPUTER CODES; DATA; ELECTROMAGNETIC RADIATION; HEATING; INFORMATION; IONIZING RADIATIONS; MATERIALS; NUCLEAR FACILITIES; POWER PLANTS; RADIATION FLUX; RADIATIONS; THERMAL POWER PLANTS; TRANSPORT THEORY 220200* -- Nuclear Reactor Technology-- Components & Accessories; 990220 -- Computers, Computerized Models, & Computer Programs-- (1987-1989)