Two-dimensional DORT discrete ordinates X-Y geometry neutron flux calculations for the Halden Heavy Boiling Water Reactor core configurations
Results are reported for two-dimensional discrete ordinates, X-Y geometry calculations performed for seven Halden Heavy Boiling Water Reactor core configurations. The calculations were performed in support of an effort to reassess the neutron fluence received by the reactor vessel. Nickel foil measurement data indicated considerable underprediction of fluences by the previously used multigroup removal- diffusion method. Therefore, calculations by a more accurate method were deemed appropriate. For each core configuration, data are presented for (1) integral fluxes in the core and near the vessel wall, (2) neutron spectra at selected locations, (3) isoflux contours superimposed on the geometry models, (4) plots of the geometry models, and (5) input for the calculations. The initial calculations were performed with several mesh sizes. Comparisons of the results from these calculations indicated that the uncertainty in the calculated fluxes should be less than 10%. However, three-dimensional effects (such as axial asymmetry in the fuel loading) could contribute to much greater uncertainty in the calculated neutron fluxes. 7 refs., 22 figs., 11 tabs.
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- DOE/NE
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 7084830
- Report Number(s):
- ORNL/TM-11513; ON: DE90014793; TRN: 90-028857
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
HBWR REACTOR
REACTOR CORES
COMPUTER CALCULATIONS
CROSS SECTIONS
D CODES
EXPERIMENTAL DATA
FUEL ELEMENTS
GEOMETRY
NEUTRON FLUX
NEUTRON SPECTRA
TWO-DIMENSIONAL CALCULATIONS
BHWR TYPE REACTORS
COMPUTER CODES
DATA
ENRICHED URANIUM REACTORS
EXPERIMENTAL REACTORS
HEAVY WATER COOLED REACTORS
HEAVY WATER MODERATED REACTORS
INFORMATION
MATHEMATICS
NUMERICAL DATA
POWER REACTORS
RADIATION FLUX
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
SPECTRA
TANK TYPE REACTORS
THERMAL REACTORS
210400* - Power Reactors
Nonbreeding
Otherwise Moderated or Unmoderated
990200 - Mathematics & Computers
220600 - Nuclear Reactor Technology- Research
Test & Experimental Reactors