Recent results from treat tests on fuel, cladding and coolant motion

Dickerman, C.E.; Barts, E.W.; Volpi, A. De; Holtz, R.E.; Murphy, William F.; Rothman, A.B.

doi:10.1016/0306-4549(76)90058-x

Cited by 4 publications

(2 citation statements)

References 3 publications

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“…The E-series tests investigated fuel dispersal and fuel thermal energy to coolant work conversion of fresh and preirradiated oxide fuel pins failing into flowing sodium in $3/s FTR overpower transients [70,71,72,73,74,75,76,77,78,79] [80,81,82,83,84,85,86]. A one-page summary of each E-series test is included in Appendix M.…”

Section: E-series Experimentsmentioning

confidence: 99%

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

Wright

Tomchik

2020

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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.

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Section: E-series Experimentsmentioning

confidence: 99%

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

Wright

Tomchik

2020

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“…Examples of reviews of the wide range of experiments on fuel/coolant interactions can be found in Witte et al (1970) and Board and Caldarola (1977) among others. However, none of the experiments and analyses on sodium and uranium dioxide showed any significant energetic interaction and most of the experts agree that energetic fuel/coolant interactions will not occur in liquidsodium LMFBRs (Fauske 1977, Board and Caldarola 1977, Dickerman et al 1976.…”

Section: Fuel Coolant Interactionmentioning

confidence: 99%

Thermo-Hydraulics of Nuclear Reactors

Brennen

2016

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This book provides a concise and up-to-date summary of the essential thermo-hydraulic analyses and design principles of nuclear reactors for electricity generation. Beginning with the basic nuclear physics, it leads through technical and quantitative analyses to descriptions of both the normal operation of the various modern nuclear reactor designs and the analyses of the possible departures from normal operation. It then describes both the postulated accident scenarios and summaries of the causes for the three major nuclear power generation accidents, Three Mile Island, Chernobyl and Fukushima as well as the major improvements to reactor safety that grew out of those analyses and accidents.

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