Massimiliano Fratoni

Associate Professor

University of California, Berkeley

United States

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Massimiliano Fratoni is an Associate Professor at the University of California, Berkeley. His research areas include uncertainty quantification in nuclear data, reactor physics, and the thermophysical properties of molten salt reactors. Recent articles authored by Dr. Fratoni focus on topics such as the verification of depletion calculations for TRISO fuel, reactor transient benchmarks, and the attractiveness of fissile materials in nuclear waste. He contributes significantly to advancements in nuclear fission technology and its future applications.

Articles (22)

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2020

Collaborators (4)

Zeyun Wu

Assistant Professor

UNITED STATES

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Lee Bernstein

Associate Professor

University of California, Berkeley

UNITED STATES

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Dan Kotlyar

Assistant Professor

Georgia Institute of Technology

UNITED STATES

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Anastasia Georgiadou

University of California, Berkeley

UNITED STATES

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Massimiliano Fratoni

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Articles (22)

A Reactor Transient Benchmark for Molten Salt Reactor Experiment Pump Transient Tests

Uncertainty quantification of Cl-35 nuclear data on a Molten Chloride Fast Reactor

Verification and Validation of Depletion Calculations for TRISO Fuel Against Data from the Second Advanced Gas Reactor Irradiation Campaign

Hermes Reactor Demonstration, Initial Startup, and Physics Testing

Influence of transmutation products on the thermophysical properties of eutectic NaCl-UCl3 fuel salt in a fast-spectrum molten salt reactor

Measurement of the energy-differential Cl35(n,p0)S35 cross section via the ratio with Li6(n,α)H3

A conservative first-collision source treatment for ray effect mitigation in discrete-ordinate radiation transport solutions

Attractiveness of Fissile Material in Nuclear Wastes from Different Fuel Cycles

Efficient continuous Energy-Multigroup hybrid depletion scheme using the Shift Monte Carlo code. Part I: Energy condensation sensitivity analysis

What is the future for nuclear fission technology? A technical opinion from the Guest Editors of VSI NFT series and the Editor of the Journal Nuclear Engineering and Design

Estimation of Waste Package Inventories and Characteristics from Different Advanced Fuel Cycles

Evaluation of dose rate and uncertainty of fuel debris in a canister for safe handling and management of damaged nuclear fuels

Hyper-fidelity depletion with discrete motion for pebble bed reactors

Proof of concept for hyper-fidelity depletion of full-scale pebble bed reactors

The corrosion effects of neutron activation of 2LiF-BeF<sub>2</sub> (FLiBe)

Reactor Physics Benchmark of the First Criticality in the Molten Salt Reactor Experiment

Analysis of the thermal feedback effect and nuclides flow effect on the fuel‐cycle characteristics of Molten Salt Reactors

Photoneutron production and characterization in fluoride-salt cooled high-temperature reactors

Development of methods for optimal assembly orificing design and application to a standing-wave Breed-and-Burn reactor

Linear optimization for predicting material compositions in molten salt reactors

Neutronic impact of Autonomous Reactivity Control system inclusion in a breed-and-burn core

Sensitivity and Uncertainty Analysis of Neutron Spectrum and DPA in a B&B Core

Collaborators (4)

Zeyun Wu

Lee Bernstein

Dan Kotlyar

Anastasia Georgiadou

Make your next move.

Massimiliano Fratoni

Research Interests

Explore related searches

Contact this professor

About

Articles (22)

A Reactor Transient Benchmark for Molten Salt Reactor Experiment Pump Transient Tests

Uncertainty quantification of Cl-35 nuclear data on a Molten Chloride Fast Reactor

Verification and Validation of Depletion Calculations for TRISO Fuel Against Data from the Second Advanced Gas Reactor Irradiation Campaign

Hermes Reactor Demonstration, Initial Startup, and Physics Testing

Influence of transmutation products on the thermophysical properties of eutectic NaCl-UCl3 fuel salt in a fast-spectrum molten salt reactor

Measurement of the energy-differential Cl35(n,p0)S35 cross section via the ratio with Li6(n,α)H3

A conservative first-collision source treatment for ray effect mitigation in discrete-ordinate radiation transport solutions

Attractiveness of Fissile Material in Nuclear Wastes from Different Fuel Cycles

Efficient continuous Energy-Multigroup hybrid depletion scheme using the Shift Monte Carlo code. Part I: Energy condensation sensitivity analysis

What is the future for nuclear fission technology? A technical opinion from the Guest Editors of VSI NFT series and the Editor of the Journal Nuclear Engineering and Design

Estimation of Waste Package Inventories and Characteristics from Different Advanced Fuel Cycles

Evaluation of dose rate and uncertainty of fuel debris in a canister for safe handling and management of damaged nuclear fuels

Hyper-fidelity depletion with discrete motion for pebble bed reactors

Proof of concept for hyper-fidelity depletion of full-scale pebble bed reactors

The corrosion effects of neutron activation of 2LiF-BeF<sub>2</sub> (FLiBe)

Reactor Physics Benchmark of the First Criticality in the Molten Salt Reactor Experiment

Analysis of the thermal feedback effect and nuclides flow effect on the fuel‐cycle characteristics of Molten Salt Reactors

Photoneutron production and characterization in fluoride-salt cooled high-temperature reactors

Development of methods for optimal assembly orificing design and application to a standing-wave Breed-and-Burn reactor

Linear optimization for predicting material compositions in molten salt reactors

Neutronic impact of Autonomous Reactivity Control system inclusion in a breed-and-burn core

Sensitivity and Uncertainty Analysis of Neutron Spectrum and DPA in a B&amp;B Core

Collaborators (4)

Zeyun Wu

Lee Bernstein

Dan Kotlyar

Anastasia Georgiadou

Make your next move.

Sensitivity and Uncertainty Analysis of Neutron Spectrum and DPA in a B&B Core