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A review on the clad failure studies
Authors:Tanweer Alam  Manabendra Pathak  Ritu Singh
Affiliation:a Department of Mechanical Engineering, Indian Institute of Technology Patna, Patliputra Colony, Patna, Bihar 800 013, India
b Atomic Energy Regulatory Board, Mumbai, India
Abstract:In this paper, an attempt has been made to systematically organize the research investigations conducted on clad tube failure, so far. Before presenting the review on the clad failure studies, an introduction to different clad materials has been added, in which the effect of alloying elements on the material properties have been presented. The literature on clad failure has been broadly categorized under the headings LOCA and RIA. The failure mechanisms like creep, corrosion and pellet-clad interaction have been discussed in details. Each subsection of the review has been provided with summary table, in which the studies are arranged in the chronological order. A small section on acceptance criteria for ECCS has also been included. The last section of the review has been dedicated to the core-degradation phenomena.
Keywords:BCC  body-centered cubic structure  BDBA  beyond design basis accident  BWR  boiling water reactor  CHF  critical heat flux  DNB  departure from nucleate boiling  ECCS  emergency core cooling system  GWD  giga Watt per day  HCP  hexagonal closed packed structure  HR  heating rate  ID  inner diameter  IOP  internal over pressure  IP  internal pressure  LMP  Larsen Miller parameter  LOCA  loss of coolant accident  LWR  light water reactors  MTU  mega ton unit  NRC  nuclear regulatory commission  OD  outer diameter  PCMI  pellet-clad mechanical interaction  PHWR  pressurized heavy water reactor  PWR  pressurized water reactor  RBMK  Reaktor Bolshoy Moshchnosti Kanalniy (high power channel-type reactor)  RIA  reactivity initiated accidents  RXA  re-crystallization annealed  SRA  stress relieved annealed  TCE  total circumferential elongation  VVER  Vodo-Vodyanoi Energetichesky Reactor(water-water energetic reactor)
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