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Reactivity Coefficient Calculation for AP1000 Reactor Using the NODAL3 Code

Surian Pinem, SP and Tagor Malem Sembiring, TMS and Tukiran Surbakti, TS and Deswandri, DW (2017) Reactivity Coefficient Calculation for AP1000 Reactor Using the NODAL3 Code. In: International Conference on Nuclear Technologies and Sciences (ICoNETS 2017), 12 Oktober 2017, Makasar - Sulawesi Selatan - Indonesia.

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Abstract

Abstract The reactivity coefficient is a very important parameter for inherent safety and stability of nuclear reactors operation. To provide the safety analysis of the reactor, the calculation of changes in reactivity caused by temperature is necessary because it is related to the reactor operation. In this paper, the temperature reactivity coefficients of fuel and moderator of the AP1000 core are calculated, as well as the moderator density and boron concentration. All of these coefficients are calculated at the hot full power condition (HFP). All neutron diffusion constant as a function of temperature, water density and boron concentration were generated by the SRAC2006 code. The core calculations for determination of the reactivity coefficient parameter are done by using NODAL3 code. The calculation results show that the fuel temperature, moderator temperature and boron reactivity coefficients are in the range between -2.613 pcm/°C to -4.657pcm/°C, -1.00518 pcm/°C to 1.00649 pcm/°C and -9.11361 pcm/ppm to -8.0751 pcm/ppm, respectively. For the water density reactivity coefficients, the positive reactivity occurs at the water temperature less than 190 °C. The calculation results show that the reactivity coefficients are accurate because the results have a very good agreement with the design value.

Item Type: Conference or Workshop Item (Paper)
Subjects: Keselamatan dan Keamanan Nuklir
Divisions: Pusat Teknologi dan Keselamatan Reaktor Nuklir
Depositing User: USER PTKRN BATAN
Date Deposited: 14 May 2018 02:13
Last Modified: 14 May 2018 02:13
URI: http://repo-nkm.batan.go.id/id/eprint/1392

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