Revisiting Insights from Three Mile Island Unit 2 Postaccident Examinations and Evaluations in View of the Fukushima Daiichi Accident

Rempe, J. L.; Farmer, M. T.; Corradini, Michael L.; Ott, L.J.; Gauntt, Randall O.; Powers, D.A.

doi:10.13182/nse12-3

Cited by 20 publications

(27 citation statements)

References 22 publications

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“…There is still a need for additional information on the high temperature degradation characteristics of FeCrAl cladding and channel boxes. The existing Zircaloy system is supported by a range of fuel bundle tests [30]. These tests with Zircaloy provide confidence in the predictions by codes such as MELCOR.…”

Section: Resultsmentioning

confidence: 94%

“…For Zircaloy cladding, there are numerous tests on its behavior under accident conditions [30]. Testing covers the heat up, burst, oxidation, melting, and relocation of the cladding.…”

Section: Fuel Degradation and Relocation Characteristicsmentioning

confidence: 99%

“…With respect to lower head failure timing, it should be noted that this is an area of continued uncertainty for both FeCrAl and Zircaloy [41]. There have been no prototypic tests for the BWR geometry [30].…”

Section: Mitigated Ltsbomentioning

confidence: 99%

See 2 more Smart Citations

Severe Accident Analysis Of BWR Core Fueled With UO<sub>2</sub>/FeCrAl with Updated Materials and Melt Properties From Experiments

Robb¹,

McMurray²,

Terrani³

2016

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Section: Resultsmentioning

confidence: 94%

“…For Zircaloy cladding, there are numerous tests on its behavior under accident conditions [30]. Testing covers the heat up, burst, oxidation, melting, and relocation of the cladding.…”

Section: Fuel Degradation and Relocation Characteristicsmentioning

confidence: 99%

See 1 more Smart Citation

Severe Accident Analysis Of BWR Core Fueled With UO<sub>2</sub>/FeCrAl with Updated Materials and Melt Properties From Experiments

Robb¹,

McMurray²,

Terrani³

2016

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“…Analyses to interpret and integrate these information sources were crucial, since insufficient data were available from any single source to uniquely define a consistent understanding about the TMI-2 accident scenario. Example insights highlighted in [3] include: • All TMI-2 fuel assemblies were damaged. Large regions of the core exceeded the melting temperature of the cladding (~1900 °C).…”

Section: Post Accident Insightsmentioning

confidence: 99%

“…Although there is still some debate about certain aspects of the TMI-2 accident [2,3], insights obtained from post-accident evaluations and enhanced simulation models provided a basis for improving plant design features, operator training, and accident mitigation strategies [4,5].…”

Section: Introductionmentioning

confidence: 99%

Instrumentation performance during the TMI-2 accident

Rempe¹,

Knudson²

2013

2013 3rd International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and Their Applications (ANIMM

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The accident at the Three Mile Island Unit 2 (TMI-2) reactor provided a unique opportunity to evaluate sensors exposed to severe accident conditions. Conditions associated with the release of coolant and the hydrogen burn that occurred during this accident exposed instrumentation to harsh conditions, including direct radiation, radioactive contamination, and high humidity with elevated temperatures and pressures. As part of a program initiated by the Department of Energy Office of Nuclear Energy (DOE-NE), a review was completed to gain insights from prior TMI-2 sensor survivability and data qualification efforts. This new effort focused upon a set of sensors that provided critical data to TMI-2 operators for assessing the condition of the plant and the effects of mitigating actions taken by these operators. In addition, the effort considered sensors providing data required for subsequent accident simulations.Over 100 references related to instrumentation performance and post-accident evaluations of TMI-2 sensors and measurements were reviewed. Insights gained from this review are summarized within this paper. As noted within this paper, several techniques were invoked in the TMI-2 post-accident program to evaluate sensor survivability status and data qualification, including comparisons with data from other sensors, analytical calculations, laboratory testing, and comparisons with sensors subjected to similar conditions in largescale integral tests and with sensors that were similar in design but more easily removed from the TMI-2 plant for evaluations. Conclusions from this review provide important insights related to sensor survivability and enhancement options for improving sensor performance. In addition, this paper provides recommendations related to sensor survivability and the data evaluation process that could be implemented in upcoming Fukushima Daiichi recovery efforts.

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The Three Mile Island Unit 2 Accident

Skillman

Rempe²

2021

Encyclopedia of Nuclear Energy

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Revisiting Insights from Three Mile Island Unit 2 Postaccident Examinations and Evaluations in View of the Fukushima Daiichi Accident

Cited by 20 publications

References 22 publications

Severe Accident Analysis Of BWR Core Fueled With UO<sub>2</sub>/FeCrAl with Updated Materials and Melt Properties From Experiments

Severe Accident Analysis Of BWR Core Fueled With UO<sub>2</sub>/FeCrAl with Updated Materials and Melt Properties From Experiments

Instrumentation performance during the TMI-2 accident

The Three Mile Island Unit 2 Accident

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