EMERGENCY COOLING IN BOILING WATER REACTORS UNDER SIMULATED LOSS-OF-COOLANT CONDITIONS. BWR-FLECHT Final Report.

Duncan, J.D.; Leonard, J.E.

doi:10.2172/4726374

Cited by 5 publications

(5 citation statements)

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“…Figure 19 summarizes As previously noted, the BWB heat transfer models for core spray and reflood are based empirically on the results of the BWB -FLECHT tests (Duncan and Leonard, 1971 The results of all participants were reasonably good, but by no means perfect . (Green and I ane, 1964, Chap.…”

Section: Refill Period Phenomenamentioning

confidence: 88%

Report to the American Physical Society by the study group on light-water reactor safety

et al. 1975

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The issue of light-water reactor (LWR) safety has been the subject of a part-time, year-long study sponsored by the American Physical Society. The goal of the study was the assessment of some of the technical aspects of the safety of large light-water nuclear power reactors typical of present commercial practice in the Unted States. The report examines issues related to safe operation of LWRs; the research and development program responsible for establishing and enhancing safety; and the consequences of accidents for public health and welfare. The report in no way deals with the need for nuclear power or its benefits, and should not be considered as a net assessment of the risks versus the benefits of nuclear reactors. Since the risks of ecological impacts of other energy technologies are not addressed, no recommendations are made concerning the specific reactor program which should be followed in the immediate future. Among the areas covered in the report are primary pressure-vessel integrity; quality assurance; accident initiation from operator error, transients, and sabotage; the adequacy of present emergency core-cooling system designs; the calculation of long-term consequences to health of one particular low-probability accidental release of radioactivity; and the experimental and calculational (computer-code-development) aspects of the present reactor safety ' We were fortunate that early in our study we were given copies in preliminary draft of the AEC-sponsored study of reactor safety (chaired by Professor Norman Rasmussen of M.E.T. , and known as WASH -1400). WASH-1400 is a detailed event-tree and fault-tree analysis of light-water reactor accident sequences. Its purpose was to make a quantitative estimate of the likelihood of accident consequences of a given severity. We did not undertake a review of that study as such, although it will be mentioned frequently in our report.The gracious hospitality of the Los Alamos Scientific Laboratory and the administrative assistance of the staff of the American Physical Society are also acknowledged. This study was supported by the National Science Foundation and the U. S. Atomic Energy Commission.The study participants have all agreed on both the broad conclusions and the more detailed individual recommendations contained in the body of the report. We believe this is significant in view of the diverse backgrounds of the group. Our individual technical expertise ranges widely, covering theoretical and experimental physics, chemistry, and engineering. While a few of the group had some background in reactor safety, the majority of the group had not previously considered these issues. Some of the group had participated in previous technical assessments of broad national issues; for sevSince this work was begun the Atomic Energy Commission has been split in two parts: the Energy Research and Development Administration (ERDA) and the Nuclear Regulatory Commission (NRC), and the exact distribution between ERDA and NRC of the responsibility that formerly resided...

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Section: Refill Period Phenomenamentioning

confidence: 88%

Report to the American Physical Society by the study group on light-water reactor safety

et al. 1975

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“…tends to offset the density decrease and high heat transfer is i wilhin the core arc degraded sufficiently that CIIF (6) ultimately ; (5)< [6) allows the large amount of stored energy within the fuel to ratures (7) (8).…”

Section: IVmentioning

confidence: 99%

“…During tends to flash violently and surges into the core region. The potential for significant cooling exists si temperature rise may be terminated (6) and the cladding temperature may be restored to the fluid saturatio coolant inventory in the lower plenum is spent from flashing, the system pressure continues to deel temperature again rises in the hotter zones of the core and experiences DNB a second time (7). The cladc rapidly until the energy redistribution within the fuel pin is complete at which time decay heat limits the ra rise (i\).…”

mentioning

confidence: 99%

Loss of coolant: control of consequence by emergency core cooling.

Brockett¹,

Griebe²,

Shumway³

et al. 1972

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“…To simplify comparison from test to test, a single thermocouple locatlon was selected for the BWR-FLECHT, Bundle SS-4. The midplane (six-foot elevation) on the hottest rod (Rod 17) represents the location of .highest temperature in the bundle at transient initiation and is thus the point of greatest interest in studies of ECC system effectiveness and behavior.…”

Section: T B Figur'e' Indicates That the Design Of Tms Bundle Resulmentioning

confidence: 99%

“…The midplane (six-foot elevation) on the hottest rod (Rod 17) represents' the locationof highest temperature in the BWR-FLECBT bundle at translent initiation and is t h i s the point of greatest interest in studies of E C C system effectiveness and behavior. Similarly, in the PWR-FLE CHT -.…”

mentioning

confidence: 99%

Effect of Geometry and Other Parameters on Bottom Flooding Heat Transfer Associated With Nuclear Fuel Bundle Simulators.

McConnell¹

1972

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EMERGENCY COOLING IN BOILING WATER REACTORS UNDER SIMULATED LOSS-OF-COOLANT CONDITIONS. BWR-FLECHT Final Report.

Cited by 5 publications

References 0 publications

Report to the American Physical Society by the study group on light-water reactor safety

Report to the American Physical Society by the study group on light-water reactor safety

Loss of coolant: control of consequence by emergency core cooling.

Effect of Geometry and Other Parameters on Bottom Flooding Heat Transfer Associated With Nuclear Fuel Bundle Simulators.

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