Comparative thermohydraulic analyses of VVER 1000 active core for two different construction types of assemblies

Author:

Perin Y.1,Nikonov S.2,Henry R.1,Pasichnyk I.1,Velkov K.1

Affiliation:

1. 1Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) gGmbH Boltzmannstraße 14, Garching Germany

2. 2National Research Nuclear University MEPhI, Moscow Russia

Abstract

AbstractThe OECD/NEA Benchmark on NPP Kalinin Unit 3 “Switching-off of one of the four operating main circulation pumps at nominal power” based on measurements is at its end phase. A new benchmark is starting based on measurements from the NPP Rostov Unit 2 “Reactivity compensation with diluted boron by stepwise insertion of control rod cluster into the VVER-1000 core”. The Rostov-2 core is loaded with assemblies of a new modern type “TVS-2M” which differs in construction in comparison with the “TVSA”-type implemented in the Kalinin-3 core. The goal of the performed study is to determine the thermohydraulic differences, during steady-state operation, between the two cores based on loads with different assembly types. Results of steady-state simulations are compared for Kalinin-3 and Rostov-2 cores, taken from the respective Benchmarks specifications. To ensure that the observed differences are coming only from the fuel assembly construction, the same axial power density is used for all cases. Calculations are done with an under-development version of the GRS system code ATHLET, which has sub-channel modeling capabilities. Thus, in addition to the typical assembly-wise models, calculations with seven assemblies modeled at the sub-channel (pin-by-pin) level were also performed and analyzed. This work will help the Benchmarks' Rostov-2 participants to set up more accurate core thermohydraulic models.

Publisher

Walter de Gruyter GmbH

Subject

Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics,Radiation

Cited by 2 articles. 订阅此论文施引文献 订阅此论文施引文献,注册后可以免费订阅5篇论文的施引文献,订阅后可以查看论文全部施引文献

1. Simulation of 3D hydraulic effects in the IR-8 reactor’s IRT-3M FA using ATHLET code;Journal of Physics: Conference Series;2020-11-01

2. Modeling the core of a lead-cooled reactor;Journal of Physics: Conference Series;2020-11-01

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