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AbstractAbstract
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Transactions of the American Nuclear Society 1975 annual meeting; New Orleans, LA; 8 Jun 1975; Published in summary form only.
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Transactions of the American Nuclear Society; v. 21 p. 483
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AbstractAbstract
No abstract available
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Published in summary form only.
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Journal of Mathematical Analysis and Applications; v. 48(2); p. 470-492
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AbstractAbstract
No abstract available
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Transactions of the American Nuclear Society 1976 international meeting; Washington, DC, USA; 14 Nov 1976; Published in summary form only.
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Transactions of the American Nuclear Society; v. 24 p. 199-201
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Melosh, R.J.
Proceedings of the conference on computational methods in nuclear engineering. Vol. II1975
Proceedings of the conference on computational methods in nuclear engineering. Vol. II1975
AbstractAbstract
[en] The most widely accepted way of solving linear equilibrium equations is Gauss decomposition. Implementation of this approach is summarized. Improved Seidel-type iterative methods are examined as an alternative. Two classes of problems are defined: one involving extremely sparse and the other, fully-populated matrices. Self-equilibration, block relaxation, interwoven iteration, hybridization, and extrapolation for improving Seidel efficiency are described. The results of experiments show the effectiveness of each device alone and several combinations. The full potential of these devices is realized when only three cycles of iteration produce the exact solution regardless of the number of equations and the initial guess for the fully-populated. Orders of magnitude reduction are attained for the sparse matrices suggesting Seidel-type iteration can involve fewer calculations than Gauss when the wavefront is large compared with the matrix order. 13 references. (U.S.)
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Source
Du Pont de Nemours (E.I.) and Co., Aiken, S.C. (USA). Savannah River Lab.; Energy Research and Development Administration, Aiken, S.C. (USA). Savannah River Operations Office; p. IV.1-IV.22; 1975; ANS computational methods in nuclear energy; Charleston, South Carolina, USA; 15 Apr 1975
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AbstractAbstract
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Original Title
Predel'nyj rezhim uravneniya kinetiki dlya reaktora
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For English translation see the journal J. Eng. Phys.
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Inzh.- Fiz. Zh; v. 23(6); p. 1130-1133
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AbstractAbstract
No abstract available
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Transactions of the American Nuclear Society 1976 international meeting; Washington, DC, USA; 14 Nov 1976; Published in summary form only.
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Transactions of the American Nuclear Society; v. 24 p. 201-202
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AbstractAbstract
[en] Short communication
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Ceske Vysoke Uceni Technicke, Prague (Czech Republic); 234 p; 30 Apr 1994; p. 59; CTU seminar 94; Prague (Czech Republic); 17-20 Jan 1994
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[en] A critical study of higher order perturbation methods for reactor analysis is made. These methods are classified as explicit, semi-implicit, and implicit, according to their ability to allow perturbative expressions to any order of approximation explicitly in terms of the perturbation. This latter condition is desirable in analytical studies or optimization searches for reactor systems. Emphasis is placed on the problem of real flux normalization. Practical first- and second-order explicit formulations are finally given, relevant to perturbations of the flux density. A typical example is described that indicates the potentiality of the so-called standard method
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Nuclear Science and Engineering; v. 67(3); p. 347-355
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AbstractAbstract
No abstract available
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Nuclear Science and Engineering; v. 55(1); p. 96-97
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AbstractAbstract
[en] The neutron equations of the nodal dynamics model are transformed into formulae similar to the equations of the one-point kinetics model by introducing the notion of local reactivities. The relation between the local reactivities and reactivity of the one-point kinetics model is derived. Possibilities of the practical application of the transformed neutron equations of the nodal dynamics model to reactor diagnostics are presented. (author)
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Annals of Nuclear Energy (Oxford); ISSN 0306-4549; 
; v. 9(5); p. 249-253
; v. 9(5); p. 249-253
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