Evaluation of neutronics parameters during RSG-GAS commissioning by using Monte Carlo code

Surian Pinem; Wahid Luthfi; Peng Hong Liem; Donny Hartanto

doi:10.1016/j.net.2023.01.008

Evaluation of neutronics parameters during RSG-GAS commissioning by using Monte Carlo code

Surian Pinem, Wahid Luthfi, Peng Hong Liem, Donny Hartanto

Research and Test Reactor Physics

Research output: Contribution to journal › Article › peer-review

2 Scopus citations

Abstract

Several reactor physics commissioning experiments were conducted to obtain the neutronic parameters at the beginning of the G.A. Siwabessy Multi-purpose Reactor (RSG-GAS) operation. These parameters are essential for the reactor to safety operate. Leveraging the experimental data, this study evaluated the calculated core reactivity, control rod reactivity worth, integral control rod reactivity curve, and fuel reactivity. Calculations were carried out with Serpent 2 code using the latest neutron cross-section data ENDF/B-VIII.0. The criticality calculations were carried out for the RSG-GAS first core up to the third core configuration, which has been done experimentally during these commissioning periods. The excess reactivity for the second and third cores showed a difference of 510.97 pcm and 253.23 pcm to the experiment data. The calculated integral reactivity of the control rod has an error of less than 1.0% compared to the experimental data. The calculated fuel reactivity value is consistent with the measured data, with a maximum error of 2.12%. Therefore, it can be concluded that the RSG-GAS reactor core model is in good agreement to reproduce excess reactivity, control rod worth, and fuel element reactivity.

Original language	English
Pages (from-to)	1775-1782
Number of pages	8
Journal	Nuclear Engineering and Technology
Volume	55
Issue number	5
DOIs	https://doi.org/10.1016/j.net.2023.01.008
State	Published - May 2023

Funding

The authors are very grateful to the RSG-GAS multipurpose reactor staff members for conducting the experiments. This research was supported by the Indonesian government through DIPA for the 2021 fiscal year funding number SP DIPA-080.01.1.450310/2021. The authors are very grateful to the RSG-GAS multipurpose reactor staff members for conducting the experiments. This research was supported by the Indonesian government through DIPA for the 2021 fiscal year funding number SP DIPA-080.01.1.450310/2021 .

Funders	Funder number
Indonesian government	SP DIPA-080.01.1.450310/2021
RSG-GAS

Keywords

Control rod worth
Fuel element reactivity
Neutronic parameter
RSG-GAS
Serpent 2

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10.1016/j.net.2023.01.008

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title = "Evaluation of neutronics parameters during RSG-GAS commissioning by using Monte Carlo code",

abstract = "Several reactor physics commissioning experiments were conducted to obtain the neutronic parameters at the beginning of the G.A. Siwabessy Multi-purpose Reactor (RSG-GAS) operation. These parameters are essential for the reactor to safety operate. Leveraging the experimental data, this study evaluated the calculated core reactivity, control rod reactivity worth, integral control rod reactivity curve, and fuel reactivity. Calculations were carried out with Serpent 2 code using the latest neutron cross-section data ENDF/B-VIII.0. The criticality calculations were carried out for the RSG-GAS first core up to the third core configuration, which has been done experimentally during these commissioning periods. The excess reactivity for the second and third cores showed a difference of 510.97 pcm and 253.23 pcm to the experiment data. The calculated integral reactivity of the control rod has an error of less than 1.0% compared to the experimental data. The calculated fuel reactivity value is consistent with the measured data, with a maximum error of 2.12%. Therefore, it can be concluded that the RSG-GAS reactor core model is in good agreement to reproduce excess reactivity, control rod worth, and fuel element reactivity.",

keywords = "Control rod worth, Fuel element reactivity, Neutronic parameter, RSG-GAS, Serpent 2",

author = "Surian Pinem and Wahid Luthfi and Liem, {Peng Hong} and Donny Hartanto",

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AB - Several reactor physics commissioning experiments were conducted to obtain the neutronic parameters at the beginning of the G.A. Siwabessy Multi-purpose Reactor (RSG-GAS) operation. These parameters are essential for the reactor to safety operate. Leveraging the experimental data, this study evaluated the calculated core reactivity, control rod reactivity worth, integral control rod reactivity curve, and fuel reactivity. Calculations were carried out with Serpent 2 code using the latest neutron cross-section data ENDF/B-VIII.0. The criticality calculations were carried out for the RSG-GAS first core up to the third core configuration, which has been done experimentally during these commissioning periods. The excess reactivity for the second and third cores showed a difference of 510.97 pcm and 253.23 pcm to the experiment data. The calculated integral reactivity of the control rod has an error of less than 1.0% compared to the experimental data. The calculated fuel reactivity value is consistent with the measured data, with a maximum error of 2.12%. Therefore, it can be concluded that the RSG-GAS reactor core model is in good agreement to reproduce excess reactivity, control rod worth, and fuel element reactivity.

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Evaluation of neutronics parameters during RSG-GAS commissioning by using Monte Carlo code

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