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Chemistry and technology of Molten Salt Reactors – history and perspectives

Journal of nuclear materials, 2007-01, Vol.360 (1), p.6-11

UHLIR, Jan

2007

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Investigation of Normal and Abnormal States of the Molten Salt Experimental Loop Using Computational Fluid Dynamics

Nuclear science and engineering, 2023-12, Vol.197 (12), p.2961-2976

2023

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Impact of reactor neutron spectrum on measured spectrum averaged cross sections

Annals of nuclear energy, 2022-12, Vol.179, p.109418, Article 109418

2022

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Validation of zirconium isotopes (n,g) and (n,2n) cross sections in a comprehensive LR-0 reactor operative parameters set

Applied radiation and isotopes, 2017-10, Vol.128, p.92-100

2017

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A reference neutron field for measurement of spectrum averaged cross sections

Annals of nuclear energy, 2020-06, Vol.140, p.107119, Article 107119

2020

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Validation of IRDFF-II library in VR-1 reactor field using thin targets

Annals of nuclear energy, 2021-08, Vol.158, p.108268, Article 108268

2021

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The molten salt reactor (MSR) in generation IV: Overview and perspectives

Progress in nuclear energy (New series), 2014-11, Vol.77, p.308-319

2014

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Fluoride volatility method for reprocessing of LWR and FR fuels

Journal of fluorine chemistry, 2009, Vol.130 (1), p.89-93

2009

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Measurement of 75As(n,2n) cross section in well-defined spectrum of LR-0 special core

Annals of nuclear energy, 2017-02, Vol.100, p.42-49

2017

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Radiolytic Production of Fluorine Gas from MSR Relevant Fluoride Salts

Nuclear science and engineering, 2023-04, Vol.197 (4), p.633-646

2023

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Speech Defect Analysis Using Hidden Markov Models

Radioengineering, 2007-04, Vol.16 (1), p.67-72

2007

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Measurement of 89Y(n,2n) spectral averaged cross section in LR-0 special core reactor spectrum

Radiation physics and chemistry (Oxford, England : 1993), 2017-12, Vol.141, p.22-28

2017

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Measurement of super(23)Na(n,2n) cross section in well-defined reactor spectra

Applied radiation and isotopes, 2016-05, Vol.111, p.1-7

2016

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Study and Application of Silence Model Adaptation for Use in Telephone Speech Recognition System

Radioengineering, 2004-09, Vol.13 (3), p.1-6

2004

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Analysis and Optimization of Telephone Speech Command Recognition System Performance in Noisy Environment

Radioengineering, 2004-04, Vol.13 (1), p.1-7

2004

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Development of Electrochemical Separation Methods in Molten LiF-NaF-KF for the Molten Salt Reactor Fuel Cycle

Journal of nuclear science and technology, 2005-12, Vol.42 (12), p.1017

2005

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Measurement of the 23Na(n,2n) cross section in 235U and 252Cf fission neutron spectra

EPJ Web of Conferences, 2017, Vol.146, p.04045

2017

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Signal Analysis and Prediction

1, 1998

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Development of Electrochemical Separation Methods in Molten LiF-NaF-KF for the Molten Salt Reactor Fuel Cycle

Journal of nuclear science and technology, 2005-12, Vol.42 (12), p.1017-1024

2005

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Measurement of (23)Na(n,2n) cross section in well-defined reactor spectra

Applied radiation and isotopes, 2016-05, Vol.111, p.1-7

2016

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Thumb Motion Classification using Discrimination Functions

2006 International Conference on Applied Electronics, 2006, p.55-57

2006

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Validation of differential cross sections by means of 252Cf spectral averaged cross sections

Applied radiation and isotopes, 2018-02, Vol.132, p.29-37

2018

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Measurement of 23Na(n,2n) cross section in well-defined reactor spectra

Applied radiation and isotopes, 2016-05, Vol.111, p.1-7

2016

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Development of Pyrochemical Reprocessing of the Spent Nuclear Fuel and Prospects of Closed Fuel Cycle

Atom Indonesia, 2007-01, Vol.33 (1), p.47-59

2007

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Chemical processing of liquid fuel

Molten Salt Reactors and Thorium Energy, 2017

Dolan, Thomas James

2017

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Chemistry and technology of Molten Salt Reactors – history and perspectives

Investigation of Normal and Abnormal States of the Molten Salt Experimental Loop Using Computational Fluid Dynamics

Impact of reactor neutron spectrum on measured spectrum averaged cross sections

Validation of zirconium isotopes (n,g) and (n,2n) cross sections in a comprehensive LR-0 reactor operative parameters set

A reference neutron field for measurement of spectrum averaged cross sections

Validation of IRDFF-II library in VR-1 reactor field using thin targets

The molten salt reactor (MSR) in generation IV: Overview and perspectives

Fluoride volatility method for reprocessing of LWR and FR fuels

Measurement of 75As(n,2n) cross section in well-defined spectrum of LR-0 special core

Radiolytic Production of Fluorine Gas from MSR Relevant Fluoride Salts

Speech Defect Analysis Using Hidden Markov Models

Measurement of 89Y(n,2n) spectral averaged cross section in LR-0 special core reactor spectrum

Measurement of super(23)Na(n,2n) cross section in well-defined reactor spectra

Study and Application of Silence Model Adaptation for Use in Telephone Speech Recognition System

Analysis and Optimization of Telephone Speech Command Recognition System Performance in Noisy Environment

Development of Electrochemical Separation Methods in Molten LiF-NaF-KF for the Molten Salt Reactor Fuel Cycle

Measurement of the 23Na(n,2n) cross section in 235U and 252Cf fission neutron spectra

Signal Analysis and Prediction

Development of Electrochemical Separation Methods in Molten LiF-NaF-KF for the Molten Salt Reactor Fuel Cycle

Measurement of (23)Na(n,2n) cross section in well-defined reactor spectra

Thumb Motion Classification using Discrimination Functions

Validation of differential cross sections by means of 252Cf spectral averaged cross sections

Measurement of 23Na(n,2n) cross section in well-defined reactor spectra

Development of Pyrochemical Reprocessing of the Spent Nuclear Fuel and Prospects of Closed Fuel Cycle

Chemical processing of liquid fuel

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