The Application of the Finite Element Method to the Multigroup Neutron Diffusion Equation
Journal Article
·
· Nuclear Science and Engineering
OSTI ID:4650979
- Northwestern Univ., Evanston, IL (United States)
Abstract not provided.
- Research Organization:
- Northwestern Univ., Evanston, IL (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); US Atomic Energy Commission (AEC)
- NSA Number:
- NSA-26-030449
- OSTI ID:
- 4650979
- Journal Information:
- Nuclear Science and Engineering, Journal Name: Nuclear Science and Engineering Journal Issue: 3 Vol. 47; ISSN 0029-5639
- Publisher:
- Taylor & Francis
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
COMPUTER CALCULATIONS
EIGENVALUES
FINITE ELEMENT METHOD
MULTIGROUP THEORY
NEUTRON DIFFUSION EQUATION
NEUTRON FLUX
NEUTRONS/diffusion equation for
formulation of finite element method for
Nuclear Criticality Safety Program (NCSP)
REACTORS
REACTORS/neutron flux distribution in
finite element method analysis of
SPATIAL DISTRIBUTION
COMPUTER CALCULATIONS
EIGENVALUES
FINITE ELEMENT METHOD
MULTIGROUP THEORY
NEUTRON DIFFUSION EQUATION
NEUTRON FLUX
NEUTRONS/diffusion equation for
formulation of finite element method for
Nuclear Criticality Safety Program (NCSP)
REACTORS
REACTORS/neutron flux distribution in
finite element method analysis of
SPATIAL DISTRIBUTION