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A COARSE MESH FINITE ELEMENT METHOD ...

ELLISON, PHILLIP GLEN.

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A COARSE MESH FINITE ELEMENT METHOD FOR BOILING WATER REACTOR PHYSICS ANALYSIS.

紀錄類型:	書目-電子資源 : Monograph/item
正題名/作者:	A COARSE MESH FINITE ELEMENT METHOD FOR BOILING WATER REACTOR PHYSICS ANALYSIS./
作者:	ELLISON, PHILLIP GLEN.
面頁冊數:	99 p.
附註:	Source: Dissertation Abstracts International, Volume: 44-09, Section: B, page: 2872.
Contained By:	Dissertation Abstracts International44-09B.
標題:	Nuclear engineering. -
電子資源:	http://pqdd.sinica.edu.tw/twdaoapp/servlet/advanced?query=8400666

A COARSE MESH FINITE ELEMENT METHOD FOR BOILING WATER REACTOR PHYSICS ANALYSIS.
ELLISON, PHILLIP GLEN.

A COARSE MESH FINITE ELEMENT METHOD FOR BOILING WATER REACTOR PHYSICS ANALYSIS. - 99 p.

Source: Dissertation Abstracts International, Volume: 44-09, Section: B, page: 2872.

Thesis (Ph.D.)--Northwestern University, 1983.

A coarse mesh method is formulated for the solution of Boiling Water Reactor physics problems using two group diffusion theory. No fuel assembly cross-section homogenization is required; water gaps, control blades and fuel pins of varying enrichments are treated explicitly. The method combines constrained finite element discretization with infinite lattice super cell trial functions to obtain coarse mesh solutions for which the only approximations are along the boundaries between fuel assemblies. The method is applied to bench mark Boiling Water Reactor problems to obtain both the eigenvalue and detailed flux distributions. The solutions to these problems indicate the method is useful in predicting detailed power distributions and eigenvalues for Boiling Water Reactor physics problems.Subjects--Topical Terms:

595435
Nuclear engineering.

A COARSE MESH FINITE ELEMENT METHOD FOR BOILING WATER REACTOR PHYSICS ANALYSIS.
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100 1 $a ELLISON, PHILLIP GLEN. $3 3178715
245 1 2 $a A COARSE MESH FINITE ELEMENT METHOD FOR BOILING WATER REACTOR PHYSICS ANALYSIS.
300 $a 99 p.
500 $a Source: Dissertation Abstracts International, Volume: 44-09, Section: B, page: 2872.
502 $a Thesis (Ph.D.)--Northwestern University, 1983.
520 $a A coarse mesh method is formulated for the solution of Boiling Water Reactor physics problems using two group diffusion theory. No fuel assembly cross-section homogenization is required; water gaps, control blades and fuel pins of varying enrichments are treated explicitly. The method combines constrained finite element discretization with infinite lattice super cell trial functions to obtain coarse mesh solutions for which the only approximations are along the boundaries between fuel assemblies. The method is applied to bench mark Boiling Water Reactor problems to obtain both the eigenvalue and detailed flux distributions. The solutions to these problems indicate the method is useful in predicting detailed power distributions and eigenvalues for Boiling Water Reactor physics problems.
590 $a School code: 0163.
650 4 $a Nuclear engineering. $3 595435
690 $a 0552
710 2 $a Northwestern University. $3 1018161
773 0 $t Dissertation Abstracts International $g 44-09B.
790 $a 0163
791 $a Ph.D.
792 $a 1983
793 $a English
856 4 0 $u http://pqdd.sinica.edu.tw/twdaoapp/servlet/advanced?query=8400666