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Towards sustainable nuclear energy: Putting nuclear physics to work

Annals of nuclear energy, 2008-11, Vol.35 (11), p.2024-2030

2008

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A Bayesian Monte Carlo method for fission yield covariance information

Annals of nuclear energy, 2016-09, Vol.95, p.125-134

2016

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Combining Total Monte Carlo and Unified Monte Carlo: Bayesian nuclear data uncertainty quantification from auto-generated experimental covariances

Progress in nuclear energy (New series), 2017-04, Vol.96, p.76-96

2017

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Nuclear data uncertainty propagation: Perturbation vs. Monte Carlo

Annals of nuclear energy, 2011-05, Vol.38 (5), p.942-952

2011

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Selecting benchmarks for reactor simulations: An application to a lead fast reactor

Annals of nuclear energy, 2016-10, Vol.96, p.158-169

2016

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Iron NRT- and arc-displacement cross sections and their covariances

Nuclear materials and energy, 2018-05, Vol.15, p.244-248

2018

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Evaluation of excitation functions of 100Mo(p,d+pn)99Mo and 100Mo (p,2n)99mTc reactions: Estimation of long-lived Tc-impurity and its implication on the specific activity of cyclotron-produced 99mTc

Applied radiation and isotopes, 2014-02, Vol.85, p.101-113

2014

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TENDL-based evaluation and adjustment of p+111Cd between 1 and 100 MeV

Applied radiation and isotopes, 2023-08, Vol.198, p.110832-110832, Article 110832

2023

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Uncertainties for criticality-safety benchmarks and distributions

Annals of nuclear energy, 2009-06, Vol.36 (6), p.810-831

2009

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Bayesian updating for data adjustments and multi-level uncertainty propagation within Total Monte Carlo

Annals of nuclear energy, 2020-05, Vol.139, p.107239, Article 107239

2020

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Neurophysiological Analysis of Cortical Myoclonic Tremor and Excessive Startle in ARHGEF9 Deficiency

Movement disorders clinical practice (Hoboken, N.J.), 2024-04, Vol.11 (4), p.434-437

2024

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Design, construction and operation of a graphite irradiation creep facility

Nuclear engineering and design, 2020-08, Vol.364, p.110588, Article 110588

2020

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Combinatorial level densities for practical applications

EPJ Web of conferences, 2010, Vol.2, p.4005

2010

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A measurement of ( n , x n γ ) cross sections for 208Pb from threshold up to 20 MeV

Nuclear physics. A, 2008-10, Vol.811 (1), p.1-27

2008

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Nuclear data uncertainty for criticality-safety: Monte Carlo vs. linear perturbation

Annals of nuclear energy, 2016-06, Vol.92, p.150-160

2016

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Irradiation of thorium-bearing molten fluoride salt in graphite crucibles

Nuclear engineering and design, 2021-04, Vol.375, p.111094, Article 111094

2021

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Study of the

Physics of atomic nuclei, 2017-05, Vol.80 (3), p.402

2017

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Study of the reactions for [sup.96,98,104]Ru and [sup.112,114,116]Sn at astrophysically relevant energies

Physics of atomic nuclei, 2017-05, Vol.80 (3), p.402

2017

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Quantification of Uncertainties due to 235,238U, 239,240,241Pu and Fission Products Nuclear Data Uncertainties for a PWR Fuel Assembly

Nuclear data sheets, 2014-04, Vol.118, p.531-534

2014

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Uncertainty and correlation analysis of lead nuclear data on reactor parameters for the European Lead Cooled Training Reactor

Annals of nuclear energy, 2015-01, Vol.75, p.26-37

2015

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Uncertainty quantification for criticality problems using non-intrusive and adaptive Polynomial Chaos techniques

Annals of nuclear energy, 2013-06, Vol.56, p.71-80

2013

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On the use of integral experiments for uncertainty reduction of reactor macroscopic parameters within the TMC methodology

Progress in nuclear energy (New series), 2016-04, Vol.88, p.43-52

2016

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Re-evaluation of the thermal neutron capture cross section of 147 Nd

Annals of nuclear energy, 2016-08, Vol.94, p.612-617

2016

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From flatness to steepness: Updating TALYS covariances with experimental information

Annals of nuclear energy, 2014-11, Vol.73, p.7-16

2014

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Re-evaluation of the thermal neutron capture cross section of 147Nd

Annals of nuclear energy, 2016-08, Vol.94, p.612-617

2016

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Towards sustainable nuclear energy: Putting nuclear physics to work

A Bayesian Monte Carlo method for fission yield covariance information

Combining Total Monte Carlo and Unified Monte Carlo: Bayesian nuclear data uncertainty quantification from auto-generated experimental covariances

Nuclear data uncertainty propagation: Perturbation vs. Monte Carlo

Selecting benchmarks for reactor simulations: An application to a lead fast reactor

Iron NRT- and arc-displacement cross sections and their covariances

Evaluation of excitation functions of 100Mo(p,d+pn)99Mo and 100Mo (p,2n)99mTc reactions: Estimation of long-lived Tc-impurity and its implication on the specific activity of cyclotron-produced 99mTc

TENDL-based evaluation and adjustment of p+111Cd between 1 and 100 MeV

Uncertainties for criticality-safety benchmarks and distributions

Bayesian updating for data adjustments and multi-level uncertainty propagation within Total Monte Carlo

Neurophysiological Analysis of Cortical Myoclonic Tremor and Excessive Startle in ARHGEF9 Deficiency

Design, construction and operation of a graphite irradiation creep facility

Combinatorial level densities for practical applications

A measurement of ( n , x n γ ) cross sections for 208Pb from threshold up to 20 MeV

Nuclear data uncertainty for criticality-safety: Monte Carlo vs. linear perturbation

Irradiation of thorium-bearing molten fluoride salt in graphite crucibles

Study of the

Study of the reactions for [sup.96,98,104]Ru and [sup.112,114,116]Sn at astrophysically relevant energies

Quantification of Uncertainties due to 235,238U, 239,240,241Pu and Fission Products Nuclear Data Uncertainties for a PWR Fuel Assembly

Uncertainty and correlation analysis of lead nuclear data on reactor parameters for the European Lead Cooled Training Reactor

Uncertainty quantification for criticality problems using non-intrusive and adaptive Polynomial Chaos techniques

On the use of integral experiments for uncertainty reduction of reactor macroscopic parameters within the TMC methodology

Re-evaluation of the thermal neutron capture cross section of 147 Nd

From flatness to steepness: Updating TALYS covariances with experimental information

Re-evaluation of the thermal neutron capture cross section of 147Nd

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