EBWR test reports /

EBWR test reports /

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Bibliographic Details
Language:	English
Format:	U.S. Federal Government Document Book E-Resource

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Removal of EBWR fuel element scale by slurry honing /
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EBWR core 1A physics analyses /
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Prototype boiling water reactor /
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BWR high-pressure coolant injection (HPCI) initiation seal-in and indication.
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Suppression pool temperature limits for BWR containments : generic technical activity A-39 /
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The EBWR : experimental boiling water reactor /
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Experiments with central superheater core CSH-1, BORAX-V /
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Investigation of distorted-geometry simulation of pool dynamics in horizontal-vent BWR containments /
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The ZrO₂ - CaO - UO₂ ceramic fuel fabrication for the EBWR spiked core elements /
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Fuel movement with control rods withdrawn at BWRS.
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Dynamic behavior of boiling reactors /
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An empirical modification of nucleation theory and its application to boiling heat transfer /
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Vacuum relief system for boiling water reactor Mark I and Mark II containments.
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Mark II containment lead plant program load evaluation and acceptance criteria.
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Catalog of nuclear reactor concepts. Part I. Homogenous and quasi-homogenous reactors. Section II. Reactors fueled with homogenous aqueous solutions and slurries /
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Investigation of distorted-geometry simulation of pool dynamics in horizontal-vent BWR containments /
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Study of 40MW pressurized water, boiling water, and organic moderated reactors for production of process steam /
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Inadvertent reduction in primary coolant inventory in boiling water reactors during shutdown and startup.
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BWR steel containment corrosion /
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The establishment and assessment of Chinshan (BWR/4) Nuclear Power Plant TRACE/SNAP model /
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Tests of defected toria-urania fuel specimiens in EBWR /
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AWRE report no. R /
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Potential for unacceptable interaction between the control rod drive scram function and non-essential control air at certain GE BWR facilities.
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Theoretical study on the transfer function of BORAX-V with central superheater /
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Final specifications for government-purchased equipment for Argonne low power reactor (ALPR) /
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Rationale for a perturbation method for analyzing fluid-structure interactions in BWR pressure-suppression containment systems /
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BWR refill-reflood program task 4.1-program plan /
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Drywell debris transport study : final report.
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Mark I containment short term program : safety evaluation report.
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