Monte-Carlo eigenvalue calculation

Brockway, D.; Soran, P.D.; Whalen, P.P.

doi:10.1007/bfb0049064

Cited by 19 publications

(22 citation statements)

References 2 publications

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“…Note the need for a larger number of MC particles compared to the time-independent alpha in Section 4.1.2. This is because the time-independent alpha procedure is more efficient and is capable of producing more accurate results according to Brockway et al (1985).…”

Section: Time-independent Eigenvalue: Population Time Constants (A)mentioning

confidence: 96%

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Monte Carlo Application ToolKit (MCATK)

Adams

Nolen

Sweezy

et al. 2015

Annals of Nuclear Energy

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Section: Time-independent Eigenvalue: Population Time Constants (A)mentioning

confidence: 96%

“…MCATK algorithms include static Keff eigenvalues using a power iteration method, and static neutron population time constants using a search method similar to the Monte Carlo eigenvalue methods described by Brockway et al (1985).…”

Section: Algorithmsmentioning

confidence: 99%

Monte Carlo Application ToolKit (MCATK)

Adams

Nolen

Sweezy

et al. 2015

Annals of Nuclear Energy

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“…Generally, the numerical integration of Boltzmann equation or Monte Carlo method is used for modeling of the reducing of neutron radiation in matter (Brockway et al, 1985). The MCNP code is a widespread program for modeling of neutron passing in matter with the help of Monte Carlo method (Briesmeister, 1993).…”

Section: Theory and Calculation For Neutron Attenuationmentioning

confidence: 99%

Radiation shielding properties of a novel cement–basalt mixture for nuclear energy applications

Ipbüker

Nulk

Gulik

et al. 2015

Nuclear Engineering and Design

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“…(1) shows that neutron weight increase or decrease when a neutron flies through a medium. If the neutron flux in the last term in Eq.…”

Section: Algorithm Of  Mode Eigenvalue Calculation In Monte Carlo Tementioning

confidence: 99%

Higher Order αMode Eigenvalue Calculation by Monte Carlo Power Iteration

Yamamoto

2011

Progress in Nuclear Science and Technology

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A recently proposed method implementing a pseudo absorption term in the neutron transport equation for  mode eigenvalue calculations in the Monte Carlo technique has been discussed. This method is known to overcome the difficulty in  mode eigenvalue calculations for fissionable systems with large subcriticality. This paper has demonstrated that this technique certainly can provide stable  mode eigenvalue calculations for problems that the original MCNP 4C fails to solve and that the figure of merit of the calculated  value is largely improved. However, caution should be taken that the variance of calculated  values is underestimated due to the inter-cycle correlation of the  values. A method that provides eigenfunctions with higher order criticality eigenvalues has been applied to the second order  mode eigenvalue calculations. The method partitions a whole space into two regions. The estimate of the multiplication factor in each region is forced to be equal to each other. This method is found to be applicable to calculations for the second  mode eigenfunction. The conditions on convergence of the second  mode eigenfunction are discussed. Hotelling's method, which explicitly subtracts lower order eigenfunctions from the fission source distribution, has been applied to a test problem. The third and fourth order forward eigenfunctions are successfully obtained with the use of Hotelling's method.

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Monte-Carlo eigenvalue calculation

Cited by 19 publications

References 2 publications

Monte Carlo Application ToolKit (MCATK)

Monte Carlo Application ToolKit (MCATK)

Radiation shielding properties of a novel cement–basalt mixture for nuclear energy applications

Higher Order αMode Eigenvalue Calculation by Monte Carlo Power Iteration

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