An Improvement of the Monte Carlo Generalized Differential Operator Method by Taking into Account First- and Second-Order Perturbations of Fission Source

Raskach, K. F.

doi:10.13182/nse162-158

Cited by 23 publications

(8 citation statements)

References 4 publications

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“…The Differential Operator Technique is applied in MCNPX-2.7e to calculate the change Δ eff due to a perturbation in a cross section, Δ , by means of the PERT card. It is based on the Taylor series expansion as presented in (9), where is the cross section perturbed, ,0 is its nominal value, and Δ = − ,0 , is the perturbation:…”

Section: Mcnpx-27e-the Differential Operator Techniquementioning

confidence: 99%

“…The second one is the derivative of the tally response itself. There is an additional derivative for the changes in the fission source distribution that MCNPX-2.7e does not take into account, but methodologies about how to calculate it have been developed in [4,[7][8][9] showing also its effect. In [4,10], it was pointed out that because the scattering affects the fission source spatial distribution more than capture, the sensitivity to scattering cross sections could be wrong.…”

Section: Mcnpx-27e-the Differential Operator Techniquementioning

confidence: 99%

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Propagation of Cross-Section Uncertainties in Criticality Calculations in the Framework of UAM-Phase I Using MCNPX-2.7e and SCALE-6.1

Díez

Herrero

Cabellos

et al. 2013

Science and Technology of Nuclear Installations

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In the framework of the OECD/NEA project on Benchmark for Uncertainty Analysis in Modeling (UAM) for Design, Operation, and Safety Analysis of LWRs, several approaches and codes are being used to deal with the exercises proposed in Phase I, “Specifications and Support Data for Neutronics Cases.” At UPM, our research group treats these exercises with sensitivity calculations and the “sandwich formula” to propagate cross-section uncertainties. Two different codes are employed to calculate the sensitivity coefficients ofkeffto cross sections in criticality calculations: MCNPX-2.7e and SCALE-6.1. The former uses the Differential Operator Technique and the latter uses the Adjoint-Weighted Technique. In this paper, the main results for exercise I-2 “Lattice Physics” are presented for the criticality calculations of PWR. These criticality calculations are done for a15×15TMI fuel assembly at four different states: HZP-Unrodded, HZP-Rodded, HFP-Unrodded, and HFP-Rodded. The results of the two different codes above are presented and compared. The comparison proves a good agreement between SCALE-6.1 and MCNPX-2.7e inkeffuncertainty that comes from the sensitivity coefficients calculated by both codes. Differences are found when the sensitivity profiles are analysed, but they do not lead to differences in thekeffuncertainty.

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Section: Mcnpx-27e-the Differential Operator Techniquementioning

confidence: 99%

Section: Mcnpx-27e-the Differential Operator Techniquementioning

confidence: 99%

Propagation of Cross-Section Uncertainties in Criticality Calculations in the Framework of UAM-Phase I Using MCNPX-2.7e and SCALE-6.1

Díez

Herrero

Cabellos

et al. 2013

Science and Technology of Nuclear Installations

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“…Nevertheless, the inaccuracy in the differential operator method is caused by neglecting the perturbation of the fission source distribution that cannot be taken into account unless a special technique is employed for considering the perturbation. A method for implementing the source perturbation effect was developed in (Nagaya and Mori, 2005;Nagaya and Mori, 2011;Nagaya et al, 2015;Raskach, 2009). However, the method requires the iteration procedure similar to IFP to obtain the converged perturbed fission source distribution.…”

Section: Introductionmentioning

confidence: 99%

Eigenvalue sensitivity analysis capabilities with the differential operator method in the superhistory Monte Carlo method

Yamamoto

2018

Annals of Nuclear Energy

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This paper applies the first-order differential operator method to the Monte Carlo keff-eigenvalue sensitivity analyses. The effect of the perturbed fission source distribution due to the change of a cross section on the sensitivity coefficients can be accurately estimated by introducing the source perturbation iteration method. However, a prohibitively huge memory is required for the source perturbation iteration method if a large number of sensitivity coefficients are calculated at the same time. For a reduction

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“…In the keff-eigenvalue problems, the fission source spatial distribution is also perturbed due to the perturbation of system parameters such as cross sections and material density. To estimate the effect of the fission source perturbation, some techniques have been developed and installed into Monte Carlo codes [8,9,17].…”

Section: Introductionmentioning

confidence: 99%

Improvement and performance evaluation of the perturbation source method for an exact Monte Carlo perturbation calculation in fixed source problems

Sakamoto¹,

Yamamoto

2017

Journal of Computational Physics

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This paper presents improvement and performance evaluation of the "perturbation source method", which is one of the Monte Carlo perturbation techniques. The formerly proposed perturbation source method was first-order accurate, although it is known that the method can be easily extended to an exact perturbation method. A transport equation for calculating an exact flux difference caused by a perturbation is solved. A perturbation particle representing a flux difference is explicitly transported in the perturbed system, instead of in the unperturbed system. The source term of the transport

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An Improvement of the Monte Carlo Generalized Differential Operator Method by Taking into Account First- and Second-Order Perturbations of Fission Source

Cited by 23 publications

References 4 publications

Propagation of Cross-Section Uncertainties in Criticality Calculations in the Framework of UAM-Phase I Using MCNPX-2.7e and SCALE-6.1

Propagation of Cross-Section Uncertainties in Criticality Calculations in the Framework of UAM-Phase I Using MCNPX-2.7e and SCALE-6.1

Eigenvalue sensitivity analysis capabilities with the differential operator method in the superhistory Monte Carlo method

Improvement and performance evaluation of the perturbation source method for an exact Monte Carlo perturbation calculation in fixed source problems

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