An In-Pile Study of Thermal Interactions Between . High-Energy Molten UO<sub>2</sub> Fuel and Liquid Sodium

Zivi, S.M.; Epstein, Michael; Wright, Robert; Barghusen, J.J.; Cho, D. H.; Testa, F.J.; Goldfuss, G.T.; Mouring, R.W.

doi:10.13182/nse75-a26737

Cited by 2 publications

(1 citation statement)

References 0 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…The S-series tests investigated the energetics due to thermal interaction between oxide fuel and sodium following cladding failure, over severe fuel heating scenarios and coolant conditions at cladding failure [111,112]. A one-page summary of each S-series test is included in Appendix R.…”

Section: S-series Experimentsmentioning

confidence: 99%

Transient Testing of Nuclear Fuels Performed in the Original Operation of TREAT (2nd ed.)

Wright

Tomchik

2020

View full text Add to dashboard Cite

This report provides summary information on experiments performed in the Transient Reactor Test Facility (TREAT) during its original operation from 1959-1994, and more specifically, before the TREAT core was upgraded at the end of the 1980s. The tests performed since about 1970 are summarized in considerable detail. Earlier tests are noted by their designated series and by some parameters that help to identify and distinguish each series from the others. The detailed summary descriptions are intended to help inform future researchers regarding the large, historical, empirical data base generated from that 35-year span during which hundreds of TREAT experiments were performed to investigate and demonstrate the transient behavior of a wide variety of nuclear fuels during severe off-normal and accident conditions-using direct nuclear heating of the test samples. That empirical basis is foundational and valuable for guiding future qualification and safety evaluation of improved fuel designs and for future transient test planning and performance in TREAT.

show abstract

Section: S-series Experimentsmentioning

confidence: 99%

Transient Testing of Nuclear Fuels Performed in the Original Operation of TREAT (2nd ed.)

Wright

Tomchik

2020

View full text Add to dashboard Cite

show abstract

Physics of liquid metal fast breeder reactor safety

Wilson

1977

Rev. Mod. Phys.

View full text Add to dashboard Cite

An In-Pile Study of Thermal Interactions Between . High-Energy Molten UO₂ Fuel and Liquid Sodium

Cited by 2 publications

References 0 publications

Transient Testing of Nuclear Fuels Performed in the Original Operation of TREAT (2nd ed.)

Transient Testing of Nuclear Fuels Performed in the Original Operation of TREAT (2nd ed.)

Physics of liquid metal fast breeder reactor safety

Contact Info

Product

Resources

About

An In-Pile Study of Thermal Interactions Between . High-Energy Molten UO2 Fuel and Liquid Sodium

Cited by 2 publications

References 0 publications

Transient Testing of Nuclear Fuels Performed in the Original Operation of TREAT (2nd ed.)

Transient Testing of Nuclear Fuels Performed in the Original Operation of TREAT (2nd ed.)

Physics of liquid metal fast breeder reactor safety

Contact Info

Product

Resources

About

An In-Pile Study of Thermal Interactions Between . High-Energy Molten UO₂ Fuel and Liquid Sodium