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15.05.2021 | History

2 edition of A Review of Containment Thermal-hydraulic Loading Uncertainties in Severe Accidents (Reports) found in the catalog.

A Review of Containment Thermal-hydraulic Loading Uncertainties in Severe Accidents (Reports)

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        StatementAEA Technology Plc
        PublishersAEA Technology Plc
        Classifications
        LC ClassificationsDecember 31, 1990
        The Physical Object
        Paginationxvi, 64 p. :
        Number of Pages98
        ID Numbers
        ISBN 100853563535
        Series
        1nodata
        2
        3

        nodata File Size: 7MB.


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The WIMS-D Library Update WLUP 69-group microscopic cross section library is used. Analysis of Fukushima Daiichi Accident In Unit 1, loss of DC power for both motive force and instrumentation due to flooding substantially increased the difficulty of controlling the accident. A similar portable skid-mounted water treatment and desalination system is being used to reduce contamination and chlorine levels in the SFPs of Units 2, 3, and 4.

The containment vent design, with valves that need DC power and compressed air or nitrogen to operate, plus an in-line rupture disk with a setpoint greater than the containment design pressure that cannot be bypassed, led to containment pressures well in excess of the design pressure because of delays.

The availability of AC power gave these units the ability to depressurize the reactors. The Event The earthquake occurred at 2:46 p. NPP Hardware Design Modifications Analysis of the Fukushima Daiichi accident has identified a series of hardware-related modifications, which may be addressed by near-term regulation.

REGDOC

The description of the risk-informed method shall be submitted to STUK for approval during construction and the application for information no later than with the submission of the Operational Limits and Conditions document. Consideration is also given to the extent to which generic or outstanding safety issues have been resolved.

The Turning Point From the first moments of the Fukushima Daiichi accident, the specter of Chernobyl drove much of the conversation and speculation. The initial draft of the Canadian SDO report, as found in, Attachment A-SDO Report, was presented to the CNSC and the SDO CCT at the February 2011 meeting in Seattle for review and comment.

DESIGN FEATURES OF PRESSURIZED WATER SMR CONCEPTS CONTRIBUTING TO LEVEL 1 OF DEFENCE IN DEPTH Design features What is targeted SMR designs 1 Elimination of liquid boron reactivity control system Exclusion of inadvertent reactivity insertion as a result of boron dilution KLT-40S, CAREM-25, SCOR 2 Relatively low core power density Larger thermal-hydraulic margins MARS, IRIS, CAREM-25, SCOR 3 Integral design of primary circuit with in-vessel location of steam generators and hydraulic control rod drive mechanisms Exclusion of large-break loss of coolant accidents LOCAexclusion of inadvertent control rod ejection, larger coolant inventory and thermal inertia CAREM-25, IRIS, SCOR 4 Compact modular design of the reactor unit, eliminating long pipelines in the reactor coolant system Decreased probability of LOCA KLT-40S 5 Primary pressure boundary enclosed in a pressurized, low enthalpy containment Elimination of LOCA resulting from failure of the primary coolant pressure boundary, elimination of control rod ejection accidents MARS 6 Leaktight reactor coolant system welded joints, packless canned pumps, and leaktight bellows, sealed valves, etc.

The annexes provide descriptions of the design features of 11 representative SMR concepts used to achieve defence in depth and patterned along a common format reflecting the definitions and recommendations of the IAEA safety standards. The basic design of emergency core cooling system s including how this system will be a barrier to core damage• decontamination to allow reinforcement of the weakened structures and installation of cooling and gas management systems• However, one EDG of Unit 6 was air cooled not dependent on cooling water and was located at a higher elevation, so it was able to supply emergency AC power to both Units 5 and 6.

These reports presented the design and technology development status and design descriptions for concepts of innovative SMRs developed worldwide. Support and interfacing systems to the emergency heat removal systems• Finally, the Committee focused on risk communication and crisis communication as major issues that ANS as a professional society needs to address in the future.

The operation of the HPCI system apparently also had the side benefit of reducing the RPV pressure because of the steam consumption by the HPCI turbine seven times larger than that of the RCIC system. However, the evidence is that no damage occurred to the fuel in the Unit 5 SFP, the Unit 6 SFP, or the common SFP.