1998
DOI: 10.1016/s0306-4549(97)00126-6
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Development of a computer code to estimate the fuel rod failure using primary coolant activities of operating PWRS

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Cited by 14 publications
(2 citation statements)
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“…Table 1 shows some of the design specifications of such a system. For modeling the fission product inventory in the fuel, the standard equations have been extended (Chun et al, 1998) as: where, N F,i h No. of ith radionuclide atoms in fuel (indicated by subscript F), F h average fission rate (fissions/W s), Y i h fission yield of the ith radionuclide, f ij h i / j branching ratio, s i h microscopic abs.…”
Section: Kinetics Of Fission Product Activitymentioning
confidence: 99%
“…Table 1 shows some of the design specifications of such a system. For modeling the fission product inventory in the fuel, the standard equations have been extended (Chun et al, 1998) as: where, N F,i h No. of ith radionuclide atoms in fuel (indicated by subscript F), F h average fission rate (fissions/W s), Y i h fission yield of the ith radionuclide, f ij h i / j branching ratio, s i h microscopic abs.…”
Section: Kinetics Of Fission Product Activitymentioning
confidence: 99%
“…The problem is that the degree of severity of cladding failures is not always sufficiently obvious for the operator to choose one of the two above interventions because severity varies over time; the severity is not always clear, except with the opportunities of water sampling for monitoring, although many efforts have been made to establish a method to predict the future behavior of fuel claddings during use in a reactor [6][7][8][9][10][11]. Therefore, actual operator interventions become too conservative unless an appropriate prediction method is well established.…”
Section: Introductionmentioning
confidence: 99%