Monte Carlo analysis of reactivity coefficients in fast reactors general theory and applications
- Univ. of Illinois, Urbana-Champaign, IL (United States)
Recent design studies for fast power reactors 61,63,84,93 have pointed out the difficulty of achieving reactor stability. In each design, neutron economy had to be compromised in order to achieve a stable reactor system.
- Research Organization:
- Argonne National Lab. (ANL), Argonne, IL (United States)
- Sponsoring Organization:
- US Atomic Energy Commission (AEC)
- DOE Contract Number:
- W-31-109-ENG-38
- NSA Number:
- NSA-22-001878
- OSTI ID:
- 4500721
- Report Number(s):
- ANL-7307
- Resource Relation:
- Other Information: Thesis. UNCL. Orig. Receipt Date: 31-DEC-68
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
AMC-CODE
BOLTZMANN EQUATION
DETERMINATION
DIFFERENTIAL EQUATIONS
DOPPLER EFFECT
EQUATIONS
FAST NEUTRONS
FUEL ELEMENTS
MONTE CARLO METHOD
NEUTRONS
NUMERICALS
PROBABILITY
PROGRAMMING
REACTORS
SOLUTIONS
SPACE
SPECTRAL SHIFT
STATISTICS
STOCHASTIC PROCESSES
TRANSPORT THEORY
VARIATIONS
VELOCITY
REACTORS
FAST/neutron Doppler coefficient in
effects of varying fuel element diameter on
REACTORS
FAST/kinetics equations for
solution by indirect analogy technique to
COMPUTER PROGRAMS/AMC
for solving Boltzmann equation for fast reactor kinetics
AMC-CODE
BOLTZMANN EQUATION
DETERMINATION
DIFFERENTIAL EQUATIONS
DOPPLER EFFECT
EQUATIONS
FAST NEUTRONS
FUEL ELEMENTS
MONTE CARLO METHOD
NEUTRONS
NUMERICALS
PROBABILITY
PROGRAMMING
REACTORS
SOLUTIONS
SPACE
SPECTRAL SHIFT
STATISTICS
STOCHASTIC PROCESSES
TRANSPORT THEORY
VARIATIONS
VELOCITY
REACTORS
FAST/neutron Doppler coefficient in
effects of varying fuel element diameter on
REACTORS
FAST/kinetics equations for
solution by indirect analogy technique to
COMPUTER PROGRAMS/AMC
for solving Boltzmann equation for fast reactor kinetics