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Title: Three-dimensional power distribution analysis

Authors:
;
Publication Date:
Research Org.:
Babcock and Wilcox Co., Lynchburg, Va. (USA). Nuclear Power Generation Div.
OSTI Identifier:
4435809
Report Number(s):
BAW-10061
NSA Number:
NSA-28-026483
Resource Type:
Technical Report
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-73
Country of Publication:
United States
Language:
English
Subject:
N77200* -Reactors-Power Reactors, Non-breeding, Light- water Moderated, Non-boiling Water-cooled; *PWR TYPE REACTORS- POWER DENSITY; DISTRIBUTION; P CODES; REACTOR CORES; THREE-DIMENSIONAL CALCULATIONS

Citation Formats

Hassan, H.A., and Wittkopf, W.A.. Three-dimensional power distribution analysis. United States: N. p., 1973. Web. doi:10.2172/4435809.
Hassan, H.A., & Wittkopf, W.A.. Three-dimensional power distribution analysis. United States. doi:10.2172/4435809.
Hassan, H.A., and Wittkopf, W.A.. Fri . "Three-dimensional power distribution analysis". United States. doi:10.2172/4435809. https://www.osti.gov/servlets/purl/4435809.
@article{osti_4435809,
title = {Three-dimensional power distribution analysis},
author = {Hassan, H.A. and Wittkopf, W.A.},
abstractNote = {},
doi = {10.2172/4435809},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri Jun 01 00:00:00 EDT 1973},
month = {Fri Jun 01 00:00:00 EDT 1973}
}

Technical Report:

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  • Three-dimensional flux and power distribution measurements in a pressurized-water power reactor present serious problems of accessibility, remote positioning, high temperature, and personnel exposure. These problems are successfully overcome by an activation-wire system which was developed and is used extensively for measurements within the core of such a reactor. Data are obtained during steady-state operation at flux levels in the range of 10/sup 12/ to l0/sup 15/ nv by simultaneous activation of 42 titanium-copper activation wires 0.020 in. in diameter. Pure copper wires are used for measurements in the range of 10/sup 9/ to 10/sup 11/ nv. A remote-drive mechanism positionsmore » the wires within 0.125-in.-diameter instrument thimbles which penetrate the reactor pressure vessel and extend vemtically through the core region. Automatic counting and data processing are used to convert the measured data into the desired forms of flux and power distribution information. The individual design problems and the equipment and tectniques used are discussed. (auth)« less
  • FLARE is an inexpensive calculational method to determine core reactivity and core power distribution. A scoping calculation of this type is valuable in appraising the physics characteristics of planned test modes of operation so that detailed analysis can be reserved for those core calculations of greater interest from either a technician or safety standpoint.GE635;IBM360;CDC7600; FORTRAN IV; GECOS (GE635), OS/360 (IBM360), and SCOPE (CDC7600); 39K and 3 tapes in addition to the system units are used on the GE635, 400K and 5 tapes or disks are required on the IBM360. 80,000 (octal) words of small core memory and 12,000 (octal) wordsmore » of large core memory are needed for the CDC7600 version.« less
  • Assessments of the ability of UK methods and data developed primarily for the low enriched uranium cycle to simulate thorium cycle HTRs haye been extended to cover reactivity and power distributions in commercial size reactors. The Fort St. Vrain 330 MW(E) HTR being built in the United States by Gulf General Atomic has been chosen as a convenient object for such a study since detailed design information together with the results of GGA's own calculations have been published. The results obtained are in good agreement with those obtained by GGA and indicate that both thorium and low enriched cycle HTRsmore » can be adequately modelled with UK data and methods.« less