Radial power distribution optimisation for the VVER-1000 initial core loading pattern

被引：0

作者：

Shauddin S.M. ^{[1
]}

机构：

[1] Institute of Nuclear Science and Technology, Atomic Energy Research Establishment, Ganakbari, Savar Upazila, Dhaka

来源：

International Journal of Nuclear Energy Science and Technology | 2023年 / 16卷 / 03期

关键词：

activity accumulation; burnup calculation; cold zero power; core loading pattern; CZP; enrichment zoning; HFP; hot full power; initial core; MCNP; R&R; radial power distribution; reference and reconfigured; VVER-1000;

D O I：

10.1504/IJNEST.2023.135378

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

Optimising the Radial Power Distribution (RPD) of the VVER-1000 Reference and Reconfigured (R&R) cores has been studied herein for the initial core loading pattern using the code MCNP. Optimisation of the relative RPD at Cold Zero Power (CZP) and Hot Full Power (HFP) is achieved only by means of enrichment zoning with core configurations other than that of the reference core. Fuel burnup calculation of the R&R cores was also performed to determine the core lifetime and activity accumulation. The best configuration (Config-2) shows excellent RPD over the core compared to the R&R cores without significantly disrupting the excess reactivity of the core and neutron flux. The radial power peaking factors of this configuration are about 1.6 and 1.2 times lower than the reference core at critical CZP and HFP, respectively. The lifetime of the initial loading of the core is about 50 GW days longer than the reference core. Copyright © 2023 Inderscience Enterprises Ltd.

引用

页码：206 / 215

页数：9

共 11 条

[1]

Briemeister J.F., MCNPX a General Monte Carlo N-particle Transport Code, (2013)

[2]

Chadwick M.B., Et al., ENDF/B-VII.0: next generation evaluated nuclear data library for nuclear science and technology, Nuclear Data Sheets, 107, 12, pp. 2931-3060, (2006)

[3]

Delfin-Loya A., Et al., Verification of a Triga Mark III MCNP model for neutron flux calculations, International Journal of Nuclear Energy Science and Technology, 10, 2, pp. 146-163, (2016)

[4]

Hartanto D., Et al., Neutronics assessment of accident-tolerant fuel in Advanced Power Reactor 1400 (APR1400), Atom Indonesia, 46, 3, pp. 177-186, (2020)

[5]

Hosseini M.M., Vosough N., Development of a VVER-1000 core loading pattern optimization program based on perturbation theory, Annals of Nuclear Energy, 39, pp. 35-41, (2012)

[6]

In-Core Fuel Management Code Package Validation for WWERs IAEA-TECDOC-847, (1995)

[7]

NISTIR5078-Tab3.pdf, National Institute of Standard and Technology, (2023)

[8]

Pazirandeh A., Tayefi S., Optimizing the fuel management in a VVER-1000 reactor using an artificial neural network, Annals of Nuclear Energy, 42, pp. 112-118, (2012)

[9]

Pirouzmand A., Kazem Dehdashti M., Estimation of relative power distribution and power peaking factor in a VVER-1000 reactor core using artificial neural networks, Progress in Nuclear Energy, 85, pp. 17-27, (2015)

[10]

Shauddin S.M., Et al., Criticality benchmark analysis of VVER-1000 fresh fuel assembly with MCNP, International Journal of Nuclear Energy Science and Technology, 11, 2, pp. 175-182, (2017)

← 1 2 →