Results 61 to 70 of about 788 (153)
, 2010 Calculation of the neutron flux in a nuclear reactor core is ideally performed by solving the neutron transport equation for a detailed-geometry model using several tens of energy groups.
Patel, Amin
core
DIFF, a code to prepare neutron diffusion theory parameters from the results of the code WDSN.
, 1967 With a solution of the multigroup neutron transport equation available for a problem in one dimensional geometry, diffusion theory parameters are determined so as to reproduce in diffusion theory the essential characteristics of the transport solution ...
Manning, G, Spinks, N
core
Computation system for nuclear reactor core analysis. [LMFBR]
, 1977 This report documents a system which contains computer codes as modules developed to evaluate nuclear reactor core performance. The diffusion theory approximation to neutron transport may be applied with the VENTURE code treating up to three dimensions ...
Cunningham, G. W. +7 more
core +1 more source
BN theory: Advances and new models for neutron leakage calculation
, 1997 Nuclear reactor physics design and analysis requires broad knowledge of parameters affecting reactor operation Power distributions, control rod worth, shut down margins, isotopic depletion rates, etc, have to be determined throughout the reactor cycle ...
Petrović, Ivan M., Benoist, Pierre
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Numerical Methods for Neutron Transport Calculations of Nuclear Reactors [PDF]
, 2014 The objective of this thesis, which in clearly inspired by an industrial framework, is to try and narrow the gap between theoretical neutron modelling and application in the context of nuclear reactor design.
Barbarino, Andrea
core +1 more source
Quasi-static Methods in Neutron Transport
, 2012 The present work represents a little but valuable contribution to the advancement of the research in the field of the neutron kinetics of innovative nuclear reactors.
Alcaro, Fabio
core
, 2020 Thesis: Ph. D., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, February, 2020Cataloged from student-submitted PDF version of thesis.Includes bibliographical references (pages 209-214).In nuclear reactor physics ...
Liu, Zhaoyuan,Ph. D.Massachusetts Institute of Technology.
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Complex problems arising in the collision probability theory for neutron transport [PDF]
, 2007 Several comprehensive but time consuming neutronic codes are available for performing nuclear reactor and fuel cycle evaluations. In addition, simple models utilizing collision probability theory are used to perform similar tasks with reasonable accuracy.
Matavosian, Robert
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Study of reactor constitutive model and analysis of nuclear reactor kinetics by fractional calculus approach [PDF]
, 2014 The diffusion theory model of neutron transport plays a crucial role in reactor theory since it is simple enough to allow scientific insight, and it is sufficiently realistic to study many important design problems. The neutrons are here characterized by
Patra, Ashrita
core
IMPROVED COMPUTATIONAL NEUTRONICS METHODS AND VALIDATION PROTOCOLS FOR THE ADVANCED TEST REACTOR [PDF]
, 2012 The Idaho National Laboratory (INL) is in the process of modernizing the various reactor physics modeling and simulation tools used to support operation and safety assurance of the Advanced Test Reactor (ATR).
Steuhm, Kevin A. +4 more
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