A5062041284- Nuclear reactor physics and engineering
- Nuclear Physics and Applications
- Graphite, nuclear technology, radiation studies
- Nuclear Materials and Properties
- Nuclear and radioactivity studies
- Nuclear Engineering Thermal-Hydraulics
- Radiation Detection and Scintillator Technologies
- Nuclear physics research studies
- Probabilistic and Robust Engineering Design
- Fault Detection and Control Systems
- Non-Destructive Testing Techniques
- Particle accelerators and beam dynamics
- Radioactive Decay and Measurement Techniques
- Microstructure and Mechanical Properties of Steels
- Advanced Data Processing Techniques
- Radiative Heat Transfer Studies
- Calibration and Measurement Techniques
- Structural Health Monitoring Techniques
- Radioactivity and Radon Measurements
- Spacecraft and Cryogenic Technologies
- Diverse Scientific and Engineering Research
- Matrix Theory and Algorithms
- Energy Load and Power Forecasting
- Methane Hydrates and Related Phenomena
- Metallurgical Processes and Thermodynamics
University of Tennessee at Knoxville
2020-2025
Knoxville College
2024
Naval Research Laboratory Information Technology Division
2022
Massachusetts Institute of Technology
2010-2022
Oak Ridge National Laboratory
2014-2021
National Technical Information Service
2020
International Atomic Energy Agency
2018
UT-Battelle
2015
Nuclear Energy Agency
2013
We describe the new ENDF/B-VIII.0 evaluated nuclear reaction data library. fully incorporates IAEA standards, includes improved thermal neutron scattering and uses from CIELO project for reactions on 1H, 16O, 56Fe, 235U, 238U 239Pu described in companion papers present issue of Nuclear Data Sheets. The evaluations benefit recent experimental obtained U.S. Europe, improvements theory simulation. Notable advances include updated light nuclei, structural materials, actinides, fission energy...
Accurate nuclear data are essential for advances in fields related to energy, security, medicine and space exploration, with similar needs shared by multiple applications. This perspective addresses some of the latest applications suggests work ensure both near- long-term progress
Abstract The authors developed an artificial intelligence (AI)-based algorithm for the design and optimization of a nuclear reactor core based on flexible geometry demonstrated 3× improvement in selected performance metric: temperature peaking factor. rapid development advanced, specifically, additive manufacturing (3-D printing) its introduction into advanced through Transformational Challenge Reactor program have presented opportunity to explore arbitrary nuclear-heated structures. primary...
This paper discusses the design of a fast spectrum subcritical assembly utilizing genetic algorithm. The facility proposed in this would be flexible platform for expanding knowledge neutron cross sections needed next-generation reactor designs. Fast Neutron Source (FNS) composed both and thermal region to minimize amount uranium fuel reduce overall material costs while maintaining flexibility many potential cross-section experiments. FNS customizable interchangeable down 1 × 10-in.-volume...
This paper provides a template of expected uncertainties and correlations for measurements neutron-induced capture charged-particle production cross sections. Measurements performed in-beam include total absorption spectroscopy, energy detection, γ -ray direct detection. Offline activation analysis accelerator mass spectrometry. The information needed proper use the datasets in resonance region high evaluations is described, recommended are provided when specific values not available dataset.
This work serves as a proof of concept for an automated tool to assist in the evaluation experimental neutron cross section data resolved resonance range. The characterization problem is posed mixed integer nonlinear program (MINLP). Since number resonances present unknown, model must be able determine parameters properly characterize curve well calculate appropriate values those parameters. Due size and nonconvex nature parameterization, optimization formulation too difficult solve whole. A...
Our project seeks to allow coupling of differential and integral data evaluation in a continuous-energy framework use the generalized linear least-squares (GLLS) methodology TSURFER module SCALE code package update parameters resolved resonance region evaluation. We recognize that GLLS is identical mathematical description Bayesian SAMMY, SAMINT was created machinery SAMMY based on data. Traditionally, used experimental adjust nuclear parameters. Integral data, such as International...
Nuclear cross sections are basic inputs to any nuclear computation. Campaigns of experiments fitted with the parametric $R$-matrix model quantum interactions, and resulting documented---both pointwise as resonance parameters (with uncertainties)---in standard evaluated data libraries (ENDF, JEFF, BROND, JENDL, CENDL, TENDL): these constitute our common knowledge fundamental low-energy sections. In past decade, a collaborative effort has been deployed establish new cross-section library...
Monte Carlo-transport codes are designed to simulate the complex neutron transport physics associated with nuclear systems. Numerous approximations must be made by modern simulation codes, and many have been well validated. This article investigates an impactful error caused approximation in codes. The that target-at-rest is valid for neutrons at energies 400 times of thermal energy target particle found inaccurate certain scenarios. paper identifies such cases, notably TRISO fuel instances...
We establish a definite parametrization of $R$-matrix theory, which is complete and invariant. Compared to the traditional Wigner Eisenbud, our has major advantage having no arbitrary boundary condition ${B}_{c}$, being constituted scattering matrix poles ${\mathcal{E}}_{\ensuremath{\lambda}}$, are physical quantities hence invariant with choice channel radii ${a}_{c}$. Moreover, matrix, levels ${\mathcal{E}}_{\ensuremath{\lambda}}$ correspond exactly nuclear resonances. Our also global...
This paper provides a template of expected uncertainties and correlations for measurements total neutron cross-section observables by transmission. Measurements with time-of-flight mono-energetic sources are covered. The information required evaluations in the resonance region high energy is detailed, along that can be used absence other information.
A conventional Reich-Moore approximation (RMA) of R-matrix is generalized into a manifestly unitary form by introducing set resonant capture channels treated explicitly in generalized, reduced R-matrix. dramatic reduction channel space witnessed RMA, from Nc × full to Np R-matrix, where = + Nγ, and Nγ denoting the number particle γ-ray channels, respectively, due < Nγ. corresponding RMA (GRMA) N N, defined GRMA. We show that Nλ levels. This space, although not as could be significant for...
The use of gradient descent methods for optimizing k-eigenvalue nuclear systems has been shown to be useful in the past, but gradients have proved computationally challenging due their stochastic nature. ADAM is a method that accounts with This analysis uses challenge problems constructed verify if suitable tool optimize systems. able successfully using despite nature and uncertainty. Furthermore, it clearly demonstrated low-compute time, high-variance estimates lead better performance...