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 conf...
L'un des enjeux actuel de la neutronique concerne la propagation rigoureuse des incertitudes d'entré...
Thesis: Ph. D. in Computational Nuclear Science & Engineering, Massachusetts Institute of Technology...
Neutron noise in nuclear reactors is related to the fluctuations of the neutron flux that can occur ...
A primary purpose of computational models is to inform design decisions and, in order to make those ...
This study establishes a procedure for constructing explicit and adjoint-based implicit sensitivitie...
The accurate modeling of complex physical phenomena, such as radiation transport in a laboratory exp...
Uncertainty quantification has proved itself to be a more and more important aspect of the nuclear s...
MCNP6 is used to estimate uncertainties from geometric tolerances using forward and adjoint methods....
The topic of this paper is the development of sensitivity and uncertainty analysis capability to the...
Monte Carlo N-Particle Transport Code (MCNP) is a Monte Carlo computational neutron transport code w...
Evaluating uncertainties on nuclear parameters such as reactivity is a major issue for conception of...
An approach to extend the present ORNL sensitivity program to include functionals of the time-depend...
This thesis presents novel adjoint and spectral methods for the sensitivity and uncertainty (S&U) an...
The precise estimation of Pearsons correlations, also called “representativity” coefficients, betwee...
This paper presents a nuclear data sensitivity and uncertainty analysis of the effective delayed neu...
L'un des enjeux actuel de la neutronique concerne la propagation rigoureuse des incertitudes d'entré...
Thesis: Ph. D. in Computational Nuclear Science & Engineering, Massachusetts Institute of Technology...
Neutron noise in nuclear reactors is related to the fluctuations of the neutron flux that can occur ...
A primary purpose of computational models is to inform design decisions and, in order to make those ...
This study establishes a procedure for constructing explicit and adjoint-based implicit sensitivitie...
The accurate modeling of complex physical phenomena, such as radiation transport in a laboratory exp...
Uncertainty quantification has proved itself to be a more and more important aspect of the nuclear s...
MCNP6 is used to estimate uncertainties from geometric tolerances using forward and adjoint methods....
The topic of this paper is the development of sensitivity and uncertainty analysis capability to the...
Monte Carlo N-Particle Transport Code (MCNP) is a Monte Carlo computational neutron transport code w...
Evaluating uncertainties on nuclear parameters such as reactivity is a major issue for conception of...
An approach to extend the present ORNL sensitivity program to include functionals of the time-depend...
This thesis presents novel adjoint and spectral methods for the sensitivity and uncertainty (S&U) an...
The precise estimation of Pearsons correlations, also called “representativity” coefficients, betwee...
This paper presents a nuclear data sensitivity and uncertainty analysis of the effective delayed neu...
L'un des enjeux actuel de la neutronique concerne la propagation rigoureuse des incertitudes d'entré...
Thesis: Ph. D. in Computational Nuclear Science & Engineering, Massachusetts Institute of Technology...
Neutron noise in nuclear reactors is related to the fluctuations of the neutron flux that can occur ...