Meeting cross-section requirements for nuclear-energy design

Weisbin, C.R.; Saussure, G. de; Santoro, R.T.; Gilai, D.

doi:10.1016/0306-4549(82)90006-8

Cited by 6 publications

(1 citation statement)

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“…They are predominately generated with experiments that exhibit some experimental uncertainty and bias and inevitably, experimental estimates of nuclear data do not agree with each other. A simulator has to decide upon a set of nuclear data values before proceed- Table 1.2: Estimates of light-water reactor simulation uncertainties [Weisbin et al, 1982].…”

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Adjoint-Based Uncertainty Quantification with MCNP

Seifried¹

2011

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This work serves to quantify the instantaneous uncertainties in neutron transport simulations born from nuclear data and statistical counting uncertainties. Perturbation and adjoint theories are used to derive implicit sensitivity expressions. These expressions are transformed into forms that are convenient for construction with MCNP6, creating the ability to perform adjoint-based uncertainty quantification with MCNP6. These new tools are exercised on the depleted-uranium hybrid LIFE blanket, quantifying its sensitivities and uncertainties to important figures of merit. Overall, these uncertainty estimates are small (< 2%). Having quantified the sensitivities and uncertainties, physical understanding of the system is gained and some confidence in the simulation is acquired.Professor Per F Peterson, Chair Date 1 AcknowledgementsLila Chase for assisting in compiling CRSRD, providing MCNP6 source code and compile advice, and squashing a strange bug in MAKXSF. John Wagner for providing the source for his code CRSRD.

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confidence: 99%