A VVER-1000 LEU and MOX assembly computational benchmark analysis using the lattice burnup code EXCEL

Thilagam, L.; Sunny, C. Sunil; Jagannathan, V.; Subbaiah, K.V.

doi:10.1016/j.anucene.2008.12.015

Cited by 27 publications

(6 citation statements)

References 2 publications

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“…Several solutions of the benchmark are available in literature, each of which using different methods and combinations of nuclear data libraries (Kalugin et al, 2002;Petrov et al, 2013;Thilagam et al, 2009). Three of the solutions have been obtained by means of Monte-Carlo methods, while the remaining ones are based on collision probability (or similar) methodologies.…”

Section: Benchmark Modelsmentioning

confidence: 99%

SCALE and SERPENT solutions of the OECD VVER-1000 LEU and MOX burnup computational benchmark

Mercatali

Venturini

Daeubler

et al. 2015

Annals of Nuclear Energy

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Section: Benchmark Modelsmentioning

confidence: 99%

SCALE and SERPENT solutions of the OECD VVER-1000 LEU and MOX burnup computational benchmark

Mercatali

Venturini

Daeubler

et al. 2015

Annals of Nuclear Energy

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“…Figure 8 shows the variation of the k ∞ values as a function of fuel pitch for cold zero power (CZP) state and hot zero power (HZP) state of the proposed infinite fuel cell‐wise lattice. The CZP state calculation was carried when the operation fuel temperature was 300 K, while HZP state calculation when the operation fuel temperature was 1027 K. Both the calculation of CZP sate and the HZP state were performed when the 153 Xe and 149 Sm concentrations were zero and the boric acid concentration was zero 33 . The highest values of k ∞ in cold and hot zero power states are 1.4574 and 1.4291 at 15 mm and 17 mm fuel pitch, respectively.…”

Section: Resultsmentioning

confidence: 99%

Study the neutronic feasibility of using Zr as an energy regulator instead of traditional methods

2021

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Summary The control of the reactor energy increases the reactor fuel cycle time. In this work, a new method has been investigated to control the reactor energy instead of traditional methods. SERPENT2 version 2.1.30 was used to investigate the possibility of using Zirconium rods as an energy regulator in the VVER‐1000. Zirconium rods were used as water displacers. The effect of different Zr rod diameter on the infinite multiplication factor (k∞) of the reactor and the fuel concentration at different fuel burnup steps has been analyzed. Larger fuel pitches have been investigated to increase the Zr rod diameter. The main safety parameters such as the void volume reactivity coefficients, the Doppler reactivity coefficients and the Moderator temperature coefficient have been studied at different fuel pitch and different Zr rod diameter. A comparison between the effect of Zr rods and boric acid on the reactor reactivity proved the efficiency of using Zr rods as reactivity regulation.

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“…Additionally, the same problem was analyzed using various codes & data libraries over the past several years. Some of them are EXCEL (Thilagam 2009), APOLLO2 & TRIPOLI4 (Petrov 2013), MCNPX (Louis and Amin 2016), VISWAM (Khan et al 2016) & GETERA (Abuqudaira and Stogov 2018). Having been launched in December 2012, OpenMC is a fairly new Monte Carloparticle transport code (Romano and Forget 2013) which gives the user an advantage of obtaining results based on the average result of three different methods namely track length, collision probability & absorption.…”

Section: Introductionmentioning

confidence: 99%

Neutronics and burnup analysis of VVER-1000 LEU and MOX assembly computational benchmark using OpenMC Code

Imtiaj¹,

Akter²,

Fardin³

et al. 2022

NUCET

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A handful of computational benchmarks that incorporate VVER-1000 assemblies having low enriched uranium (LEU) and the mixed oxide (MOX) fuel have been put forward by many experts across the world from the Nuclear Energy Agency. To study & scrutinize the characteristics of one of the VVER-1000 LEU & MOX assembly benchmarks in different states were considered. In this work, the VVER-1000 LEU and MOX Assembly computational-benchmark exercises are performed using the OpenMC software. The work was intended to test the preciseness of the OpenMC Monte Carlo code using nuclear data library ENDF/B-VII.1, against a handful of previously obtained solutions with other computer codes. The kinf value obtained was compared with the SERPENT and MCNP result, which presented a very good similarity with very few deviations. The kinf variation with respect to burnup upto 40 MWd/kgHM was obtained for State-5 by using OpenMC code for both the LEU and MOX fuel assembly. The depletion curves of isotope concentrations against burnup upto 40 MWd/kg/HM were also generated for both the LEU and MOX fuel assembly. The OpenMC results are comparable with those of benchmark mean values. The neutron energy vs flux spectrum was also generated by using OpenMC code. Based on the OpenMC results such as kinf, burnup, isotope concentrations and neutron energy spectrum, it is concluded that the OPenMC code with ENDF/B-VII.1 nuclear data library was successfully implemented. It is planned to use OpenMC code for calculation of neutronics and burnup of the VVER-1200 reactor to be commissioned in Bangladesh by 2023/2024.

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A VVER-1000 LEU and MOX assembly computational benchmark analysis using the lattice burnup code EXCEL

Cited by 27 publications

References 2 publications

SCALE and SERPENT solutions of the OECD VVER-1000 LEU and MOX burnup computational benchmark

SCALE and SERPENT solutions of the OECD VVER-1000 LEU and MOX burnup computational benchmark

Study the neutronic feasibility of using Zr as an energy regulator instead of traditional methods

Neutronics and burnup analysis of VVER-1000 LEU and MOX assembly computational benchmark using OpenMC Code

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A VVER-1000 LEU and MOX assembly computational benchmark analysis using the lattice burnup code EXCEL

Cited by 27 publications

References 2 publications

SCALE and SERPENT solutions of the OECD VVER-1000 LEU and MOX burnup computational benchmark

SCALE and SERPENT solutions of the OECD VVER-1000 LEU and MOX burnup computational benchmark

Study the neutronic feasibility of using Zr as an energy regulator instead of traditional methods

﻿Neutronics and burnup analysis of VVER-1000 LEU and MOX assembly computational benchmark using OpenMC Code

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Neutronics and burnup analysis of VVER-1000 LEU and MOX assembly computational benchmark using OpenMC Code