Last edited by Dozuru
Thursday, July 30, 2020 | History

2 edition of calculated loss-of-coolant accident found in the catalog.

calculated loss-of-coolant accident

L. J. Ybarrondo

calculated loss-of-coolant accident

a review

by L. J. Ybarrondo

  • 58 Want to read
  • 9 Currently reading

Published by American Institute of Chemical Engineers in New York .
Written in English

    Subjects:
  • Nuclear reactors -- Cooling,
  • Nuclear reactors -- Safety measures,
  • Boiling water reactors,
  • Pressurized water reactors

  • Edition Notes

    Bibliography: p. 84-87.

    Statement[by] L. J. Ybarrondo, C. W. Solbrig [and] H. S. Isbin.
    SeriesAmerican Institute of Chemical Engineers. Monograph series, no. 7, v. 68, 1972, AIChE monograph series ;, no. 7.
    ContributionsSolbrig, C. W., joint author., Isbin, H. S.
    Classifications
    LC ClassificationsTK9212 .Y34
    The Physical Object
    Pagination99 p.
    Number of Pages99
    ID Numbers
    Open LibraryOL5299398M
    LC Control Number72080270


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Calculated loss-of-coolant accident by L. J. Ybarrondo Download PDF EPUB FB2

COVID Resources. Reliable information about the coronavirus (COVID) is available from the World Health Organization (current situation, international travel).Numerous and frequently-updated resource results are available from this ’s WebJunction has pulled together information and resources to assist library staff as they consider how to handle coronavirus.

During the blowdown phase of a large-break loss-of-coolant accident (LOCA), high-powered regions of a nuclear reactor core exceed the critical heat flux, and peak-cladding temperatures (PCTs) in the range from to deg.

C ( to deg. F) can occur before high flow rates terminate the temperature rise. The temperature entering the bottom of the channel surrounding the fuel element is the nominal room air temperature following a loss of coolant, 16°C.

This value is based on the observed long term average air temperature for the UT TRIGA Reactor Bay. The rise File Size: 1MB. Loss-of-coolant accidents (LOCAs) are a type of reactor accident that has been studied extensively. They are the prominent scenario that protection systems and operational practice are designed to respond to.

As the name suggests, a LOCA describes an event in which the coolant is lost. The results of the analyses indicate that a loss of forced coolant flow through the first wall rapidly causes dryout in the first wall cooling pipes.

Following dryout, melting in the first wall starts within about s in case of ongoing plasma burning. In Cited by: 4. PWR: Upon initiation of the accident the steam generators are isolated on the secondary side by closing the steam supply valves and the feedwater valves. BWR: Upon receipt of a reactor-vessel low-water signal the main steam isolation valves close within 10 seconds.

Feedwater flow ramps to. Back to book. chapter 3. 85 Pages. Post CHF Effects of Spacer Grids and Blockages in Rod Bundles. In the refilling and reflooding phases of a calculated loss-of-coolant accident in a pressurized water reactor Zircaloy fuel rod claddings may reach temperatures which cause them to balloon and to burst due to internal overpressure.

The data Author: L. Hochreiter, M. Loftus, F. Erbacher, P. Ihle, K. Rust. Evaluation of a PWR Spent Fuel Pool Accident Response to Loss-of-Coolant Inventory Scenarios Using MELCOR K.C.

Wagner and R.O. Gauntt, SANDIA Letter Report, Revision 4, Completed June ; pages. MELCOR was used to simulate complete- and partial-loss-of-coolant accidents in a PWR spent fuel ://   Behaviour of BWR/6 fuel during loss-of-coolant conditions G. Scatena GEC San Jose Introduction BWR/6 Fuel Performance during a LOCA Fuel Cladding Perforation Fuel-Cladding Embrittlement Conclusions BWR/6 fuel performance is investigated during a postulated loss-of-coolant ://   Loss-of-coolant accident in the fluidized bed nuclear power reactor Where decay heat generation term Q is calculated from Q Qoe o sec.

assuming that the reactor has been in operation fbr a very long time before the accident. Q) is the volumetric heat generation rate book Co.

Holman. P.: Heat Transfer. ) loss Of Coolant Accident in the Fluidized Bed. The relaxation intensity calculated using Cole-Cole's circular arc could be useful for the evaluation of the PEEK degradation. × Close The Infona portal uses cookies, i.e.

strings of   The deformation of Zircaloy-2 fuel cladding under loss-of-coolant accident transients K. Rose, and E. Hindle UKAEA Springfields Introduction Factors contributing to the high temperature strength of Zircaloy-2 Loss of ductility by exposure to steam Deformation of cladding during a LOCA Discussion The safety of the Winfrith SGHWE "An Addendum: Probabilistic Failure Analysis of a Residual Heat Removal Heat Exchanger During Postulated Loss of Coolant Accident." Proceedings of the 20th International Conference on Nuclear Engineering and the ASME Power :// Many translated example sentences containing "l'accident de perte de réfrigérant primaire" – English-French dictionary and search engine for English ://'accident+de+perte+de+réfrigérant.

The Windscale fire of 10 October was the worst nuclear accident in Great Britain's history, ranked in severity at level 5 out of a possible 7 on the International Nuclear Event Scale.

The fire took place in Unit 1 of the two-pile Windscale facility on the northwest coast of England in Cumberland (now Sellafield, Cumbria).The two graphite-moderated reactors, referred to at the time as The Chernobyl disaster was a nuclear accident that occurred on Saturday 26 Aprilat the No.

4 nuclear reactor in the Chernobyl Nuclear Power Plant, near the city of Pripyat in the north of the Ukrainian SSR. It is considered the worst nuclear disaster in history and is one of only two nuclear energy disasters rated at seven—the maximum severity—on the International Nuclear Event "Accident year loss ratio" is a term insurance companies use as an abbreviation for "the total amount of money lost to claims divided by the amount of premiums earned in a given calendar year.".