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Kurchatov, S. Yu.; Likhanskiǐ, V. V.; Sorokin, A. A.; Khoruzhii, O. V.

doi:10.1023/a:1016562228619

Cited by 7 publications

(2 citation statements)

References 2 publications

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“…   (11) The radial distribution of the heat release is represented on figure 1 [3]. It has the same form as the radial distribution of 239 Pu in the fuel pellet [4,5], and does not depend on burnup.…”

Section: Rim B  mentioning

confidence: 99%

Calculation of temperature distribution and effective temperature in high burnup fuel of WWER-1000

2018

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The problem of finding an effective temperature is highly important. This characteristic provides calculation of the power effect reactivity (PER), which defines safe and stable operation of nuclear reactor. The numerical experiment, which is considered on average and maximum heat load conditions, is put to find out changing of the effective temperature in the high burnup fuel of WWER-1000. In the course of the experiment mathematical statement of the problem is made, numerical solution of which is found with using the finite differences approximation of both control equations and border conditions. Also, the method of simple iteration is used for calculating temperature distributions, according to determination of the effective temperature. The linear approximation was obtained basing on effective and maximum temperatures depending on the burnup.

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Section: Rim B  mentioning

confidence: 99%

Calculation of temperature distribution and effective temperature in high burnup fuel of WWER-1000

2018

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“…The original TUBRNP [6] model for power and burn-up calculations included in the TRAN-SURANUS fuel performance code [7], and later also in other codes like FRAPCON3 [8], extended the RADAR model by including higher Pu isotopes, and modifying the radial shape function that accounts for resonance absorption by 238 U. TUBRNP was originally validated for UO 2 fuel in light-water reactors (LWRs) with experimental data from fuel with burn-up values between 35 and 64 MWd/kgHM. Later on, the RAPID model [9] was developed for the COSMOS code [10][11][12], PLUTON [13] was developed for the FEMAXI code [14], while a specific burn-up model for the RTOP code [15] was developed for fuel rods in Russian-type WWER reactors. RAPID was validated purely on the basis of profiles calculated by HELIOS up to 150 MWd/kgHM, while the others were validated against experimental data up to 83 MWd/kgHM.…”

Section: Introductionmentioning

confidence: 99%