Long-term aging and loss-of-coolant accident (LOCA) testing of electrical cables
Read Online

Long-term aging and loss-of-coolant accident (LOCA) testing of electrical cables U.S./French Cooperative Research Program by

  • 125 Want to read
  • ·
  • 37 Currently reading

Published by U.S. Nuclear Regulatory Commission in Washington, DC .
Written in English


  • Electric cables -- Testing,
  • Electric cables -- Reliability,
  • Nuclear power plants -- Electric equipment -- Testing,
  • Nuclear power plants -- Electric equipment -- Reliability

Book details:

Edition Notes

Statementprepared by C.F. Nelson ... [et al.] ; prepared for Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission.
ContributionsNelson, C. F., Sandia National Laboratories., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology.
The Physical Object
Paginationxvii, 133 p. :
Number of Pages133
ID Numbers
Open LibraryOL17459389M

Download Long-term aging and loss-of-coolant accident (LOCA) testing of electrical cables


Get this from a library! Long-term aging and loss-of-coolant accident (LOCA) testing of electrical cables: U.S./French cooperative research program. [C F Nelson; Sandia National Laboratories.; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology.; Institut de protection et de sureté nucléaire (France). 5) Long-Term Cooling. After any calculated successful initial operation of the ECCS, the calculated core temperature shall be maintained at an acceptable low value and decay heat removed for the extended period of time required by the long-lived radioactivity remaining in the core. 10/12/05 Course , Lecture 9 Professor Neil Todreas Quizlet is a lightning fast way to learn vocabulary. term:loca = loss of coolant accident Classes. Browse term:loca = loss of coolant accident classes. Loss of coolant accident and loss of flow accident analysis of the ARIES-AT design Conference Paper (PDF Available) in Fusion Technology 39(2) March with 97 Reads How we measure.

Best-estimate thermal-hydraulic system codes are widely used to perform safety and licensing analyses of nuclear power plants and also used in the design of advance reactors. Evaluation of the capabilities and the performance of these codes can be accomplished by comparing the code predictions with measured experimental data obtained on different test facilities. OECD/NEA Committee on the Cited by: The safety injection system provides a source of borated cooling water to counteract the effects of an unexpected loss of coolant. This constitutes a source of replacement coolant and negative reactivity that can be injected to counteract the effect of unexpected transients or the need for a . NUC_FRP_05_R5 Loss of Coolant Accident (LOCA) Regulation: Yueh, Ken: NUC_FRP_06_R3: Silicon Carbide Composite BWR Channel Development: NUC_LTO_02_R4 Long-Term Operations Aging Management: Tilley, Richard: NUC_LTO_03_R4: Long-Term Operations Enhancements and Modern Tech: Tilley, Richard: Materials Degradation and Aging. The Chernobyl disaster was a nuclear accident that occurred on Saturday 26 April , at the No. 4 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 Scale, the Location: Chernobyl nuclear power plant, .

Advanced Nuclear Technology 9 August advanced nuclear technology Action Plan Roadmap Summary OBJeCtiVes New nuclear power plants incorporating advanced lightFile Size: 3MB. In this paper a comprehensive set of the time-limited ageing analyses for justification of long-term operation of WWER/ type units will be presented. Loss-of-coolant: Nuclear scientists have always felt that the greatest risk in operating a reactor is the loss-of-coolant accident. If for some reason the flow of water is stopped or slowed -- for example if a pipe breaks -- the fissioning fuel rods could become so hot that they could melt.   We report compression set test results about one each type of silicone rubber and EPDM gasket under irradiation from Co And we also report relationships in physical property changes between irradiation and thermal treatment. Finally NICHIAS predicts long-term and emergency sealability of these gaskets from the results of : Mitsuyuki Nakano, Haruko Sasaki, Kanji Hanashima.