Derivation of the Kinetic Equations of a Nuclear Reactor Deduced from the Boltzmann Equation (in Spanish)
Journal Article
·
· Acta Cientifica Venezolana
OSTI ID:4449569
- University Central de Venezuela, Caracas (Venezuela)
Abstract not provided.
- Research Organization:
- University Central de Venezuela, Caracas (Venezuela)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- NSA Number:
- NSA-21-013995
- OSTI ID:
- 4449569
- Report Number(s):
- Acta Cient. Venezol., 16, 219-224
- Journal Information:
- Acta Cientifica Venezolana, Vol. 16; Other Information: Orig. Receipt Date: 31-DEC-67; ISSN 0001-5504
- Country of Publication:
- Spain
- Language:
- Spanish
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OSTI ID:4449569
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
ABSORPTION
BOLTZMANN EQUATION
CRITICALITY
DELAYED NEUTRONS
DIFFERENTIAL EQUATIONS
EQUATIONS
FISSION
LEAKS
LIFETIME
LOSSES
MATHEMATICS
NEUTRON FLUX
NEUTRONS
PRODUCTION
TRANSPORT
TRANSPORT THEORY
Nuclear Criticality Safety Program (NCSP)
Power Reactor Development-Kinetics & Dynamics
Absorption
Boltzmann Equation
Criticality
Delayed Neutrons
Differential Equations
Equations
Fission
Leaks
Lifetime
Losses
Mathematics
Neutron Flux
Neutrons
Production
Transport
Transport Theory
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
ABSORPTION
BOLTZMANN EQUATION
CRITICALITY
DELAYED NEUTRONS
DIFFERENTIAL EQUATIONS
EQUATIONS
FISSION
LEAKS
LIFETIME
LOSSES
MATHEMATICS
NEUTRON FLUX
NEUTRONS
PRODUCTION
TRANSPORT
TRANSPORT THEORY
Nuclear Criticality Safety Program (NCSP)
Power Reactor Development-Kinetics & Dynamics
Absorption
Boltzmann Equation
Criticality
Delayed Neutrons
Differential Equations
Equations
Fission
Leaks
Lifetime
Losses
Mathematics
Neutron Flux
Neutrons
Production
Transport
Transport Theory