Neutronic analysis of VVER-1000 fuel assembly with different types of burnable absorbers using Monte-Carlo code Serpent

Khrais, R A; Тихомиров, Г. В.; Saldikov, Ivan; Smirnov, A D

doi:10.1088/1742-6596/1189/1/012002

Cited by 11 publications

(1 citation statement)

References 10 publications

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“…Fuel rods in the tenth and eleventh rings were selected to track the flux non-uniformity. A geometry infinite in height and radius (set bc 2) (Status Report, Khoshahval et al 2016, Khrais et al 2019 was used; therefore, the values of K inf were estimated in the work. The calculations were made with 30 days of fuel cooling after every 340 effective days (Model 1) and without cooling, continuously within a four-year fuel campaign (Model 2).…”

Section: Modelmentioning

confidence: 99%

Comparison of methods for calculating the neutronic characteristics of a VVER-1200 fuel assembly

Lavronenko¹,

Savankov²,

Vnukov³

et al. 2022

NUCET

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This article presents the results of neutronic calculations of a VVER-1200 fuel assembly carried out using the multi-purpose three-dimensional continuous-energy Monte Carlo particle transport code Serpent 2. The study compares neutronic characteristics during the fuel burnup process (1) with and (2) without fuel cooling. In the first option, the FA fuel campaign was simulated with 30-day cooling periods between reactor campaigns. The second option assumed simulating the FA fuel campaign without fuel cooling. In the course of the study, the authors determined the infinite neutron multiplication factors as well as the fuel burnup dependence of the concentrations of xenon, samarium and gadolinium nuclides. In addition, it should be noted that no differences were found in the change in the concentration of gadolinium isotopes, the discrepancy in the values of the multiplication factor, and the accumulation of samarium isotopes during the campaign.

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Section: Modelmentioning

confidence: 99%

Comparison of methods for calculating the neutronic characteristics of a VVER-1200 fuel assembly

Lavronenko¹,

Savankov²,

Vnukov³

et al. 2022

NUCET

View full text Add to dashboard Cite

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Neutronic analysis of VVER-1000 MOX fuel assembly with burnable absorber Gadolinia and Erbia

Ovi¹,

Shelley²,

Prodhan³

2021

Annals of Nuclear Energy

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The use of burnable absorbers integrated into TRISO/QUADRISO particles as a reactivity control method in a pebble-bed HTR reactor fuelled with (Th,233U)O2

Kabach

Chetaine

Benchrif

et al. 2021

Nuclear Engineering and Design

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Neutronic analysis of VVER-1000 fuel assembly with different types of burnable absorbers using Monte-Carlo code Serpent

Cited by 11 publications

References 10 publications

Comparison of methods for calculating the neutronic characteristics of a VVER-1200 fuel assembly

Comparison of methods for calculating the neutronic characteristics of a VVER-1200 fuel assembly

Neutronic analysis of VVER-1000 MOX fuel assembly with burnable absorber Gadolinia and Erbia

The use of burnable absorbers integrated into TRISO/QUADRISO particles as a reactivity control method in a pebble-bed HTR reactor fuelled with (Th,233U)O2

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Neutronic analysis of VVER-1000 fuel assembly with different types of burnable absorbers using Monte-Carlo code Serpent

Cited by 11 publications

References 10 publications

﻿Comparison of methods for calculating the neutronic characteristics of a VVER-1200 fuel assembly

﻿Comparison of methods for calculating the neutronic characteristics of a VVER-1200 fuel assembly

Neutronic analysis of VVER-1000 MOX fuel assembly with burnable absorber Gadolinia and Erbia

The use of burnable absorbers integrated into TRISO/QUADRISO particles as a reactivity control method in a pebble-bed HTR reactor fuelled with (Th,233U)O2

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Comparison of methods for calculating the neutronic characteristics of a VVER-1200 fuel assembly

Comparison of methods for calculating the neutronic characteristics of a VVER-1200 fuel assembly