Fuel cycle and neutronic performance of a spectral shift molten salt reactor design

Betzler, Benjamin R.; Robertson, Sean; Davidson, Eva E.; Powers, Jeffrey J.; Worrall, Andrew; Dewan, Leslie; Massie, Mark

doi:10.1016/j.anucene.2018.04.043

Cited by 29 publications

(5 citation statements)

References 18 publications

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“…The rod radius is 1.15 cm, and the square pitch of the unit cell is 6.8 cm. The models are taken from earlier studies at ORNL (Betzler et al 2017b(Betzler et al , 2017c(Betzler et al , 2018.…”

Section: Zirconium Hydride-moderated Msr Unit Cellmentioning

confidence: 99%

Nuclear Data and Benchmarking Program: Nuclear Data Performance Assessment for Advanced Reactors

Bostelmann

Holcomb

Clarity

et al. 2019

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Section: Zirconium Hydride-moderated Msr Unit Cellmentioning

confidence: 99%

Nuclear Data and Benchmarking Program: Nuclear Data Performance Assessment for Advanced Reactors

Bostelmann

Holcomb

Clarity

et al. 2019

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“…This change more than offsets the increase in 239 Pu fission from 0.20% to 0.56%. The largest contribution from 23 Na is elastic scattering in both libraries and contributes 0.33% to the data induced uncertainty in both cases.…”

Section: Sodium Fast Reactorsmentioning

confidence: 99%

“…All three systems are considered both fresh and with depleted fuel. All MSR models are taken from earlier studies at ORNL [19][20][21][22][23][24].…”

Section: Molten Salt Reactorsmentioning

confidence: 99%

ENDF/B-VIII.0 Covariance Data Development and Testing for Advanced Reactors

Sobes

Marshall

Wiarda

et al. 2019

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This report documents the ENDF/B-VIII.0 covariance data development and testing performed at Oak Ridge National Laboratory performed under the auspices of the US Department of Energy Office of Nuclear Energy. This work supports modeling and simulation of advanced reactor designs in the US by analyzing, validating and improving the nuclear data that provide underlying physics for calculations. This report assesses nuclear data uncertainty information for neutron cross sections, provided in the form of covariance matrices, in the 2018 ENDF/B-VIII.0 library. A review and interpretation of some of the issues with the current covariance library is provided. A new approach to augment the ENDF/B-VIII.0 covariance matrix to accurately reflect uncertainties in the results of modeling and simulation reliant on the current nuclear data library is documented. Rigorous testing of the ENDF/B-VIII.0 covariance data is documented. Finally, the performance of the ENDF/B-VIII.0 covariance data for advanced reactor applications is assessed.

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“… Isotopics. The isotopic abundances have been investigated by collaborators at ORNL (Betzler et al, 2017a;Betzler et al, 2017b;Betzler et al, 2018).  Impurities.…”

Section: Package Contentmentioning

confidence: 99%

Identification of Potential Waste Processing and Waste Form Options for Molten Salt Reactors

Riley

McFarlane

DelCul

et al. 2018

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Fuel cycle and neutronic performance of a spectral shift molten salt reactor design

Cited by 29 publications

References 18 publications

Nuclear Data and Benchmarking Program: Nuclear Data Performance Assessment for Advanced Reactors

Nuclear Data and Benchmarking Program: Nuclear Data Performance Assessment for Advanced Reactors

ENDF/B-VIII.0 Covariance Data Development and Testing for Advanced Reactors

Identification of Potential Waste Processing and Waste Form Options for Molten Salt Reactors

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