NUMERICAL SOLUTION OF THE ONE-GROUP SPACE-INDEPENDENT REACTOR KINETICS EQUATIONS FOR NEUTRON DENSITY GIVEN THE EXCESS REACTIVITY [electronic resource]

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Bibliographic Details
Online Access: Online Access
Corporate Author: Argonne National Laboratory (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: Washington, D.C. : Oak Ridge, Tenn. : United States. Department of Energy. ; distributed by the Office of Scientific and Technical Information, U.S. Department of Energy, 1960.
Subjects:

MARC

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245 0 0 |a NUMERICAL SOLUTION OF THE ONE-GROUP SPACE-INDEPENDENT REACTOR KINETICS EQUATIONS FOR NEUTRON DENSITY GIVEN THE EXCESS REACTIVITY  |h [electronic resource] 
260 |a Washington, D.C. :  |b United States. Department of Energy. ;  |a Oak Ridge, Tenn. :  |b distributed by the Office of Scientific and Technical Information, U.S. Department of Energy,  |c 1960. 
300 |a Pages: 15 :  |b digital, PDF file. 
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500 |a Published through SciTech Connect. 
500 |a 02/01/1960. 
500 |a "anl-6132" 
500 |a Kaganove, J.J. 
520 3 |a The advantages and shortcomings of the codes currently in use at Argonne (RE-13 and RE-129) are discussed. A new method of solution, which has increased accuracy, stability for exceptionally large integration intervals, and a procedure for automatically changing the integration interval as the nature of the problem changes, is developed. (auth) 
536 |b W-31-109-ENG-38. 
650 7 |a Group Theory.  |2 local. 
650 7 |a Mathematics.  |2 local. 
650 7 |a Neutron Flux.  |2 local. 
650 7 |a Numericals.  |2 local. 
650 7 |a Reactivity.  |2 local. 
650 7 |a Reactors.  |2 local. 
650 7 |a Reactor Technology.  |2 edbsc. 
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