Evaluation of Equilibrium Core Operation of the RSG-Gas Reactor

Kuntoro, Iman; Pinem, Surian; Sembiring, Tagor Malem; Haryanto, Dwi; Purwanto, Sigit

doi:10.17146/tdm.2021.23.1.6150

Cited by 3 publications

(2 citation statements)

References 8 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…The fuel loading pattern is 5/1 with the maximum burnup class is 56%. The accuracy of loading pattern 5/1 has been proved from measurements of core excess reactivity and control rod worth that is always consistent at each operation cycle [21]. Based on the measurements of several operation cycles, core formation at BOC has nearly the same core excess reactivity at every cycle.…”

Section: Methodsmentioning

confidence: 88%

Effect of New Cross Section Data File on the Criticality of the RSG-GAS Research Reactor

Kuntoro¹,

Pinem²,

Surbakti³

et al. 2023

Proceedings of the 4th International Conference on Science and Technology Applications, ICoSTA 2022, 1-2 November 2022, Medan,

View full text Add to dashboard Cite

The 30 MW RSG-GAS reactor, is routinely operated with a cycle of 600 MWD. At the end of the cycle, a new reactor core is built for the next cycle operation. Twelve fuel elements are taken out from the core. Then, the fuel elements are inserted one by one until a certain excess reactivity is achieved, according to loading steps from calculations. The research aims to evaluate the criticality experiment data of the reactor core by calculation using the new cross-section data generated from the newest ENDF/B-VIII.0 by Serpent 2. The calculations were done by the Batan-FUEL code. By using the existing cross-section, the critical conditions occurred at insertion step no. 3, while with the new cross-section critical occurred at step no. 4. The experiment reaches critical conditions at step no. 5. It shows that criticality calculation results are closer to the experiment value when using the new cross-section data.

show abstract

Section: Methodsmentioning

confidence: 88%

Effect of New Cross Section Data File on the Criticality of the RSG-GAS Research Reactor

Kuntoro¹,

Pinem²,

Surbakti³

et al. 2023

Proceedings of the 4th International Conference on Science and Technology Applications, ICoSTA 2022, 1-2 November 2022, Medan,

View full text Add to dashboard Cite

show abstract

“…The surveillance records are provided in the form of records in the operation master book and since 2014, it has been provided in the form of 'Reactor Mobile Control Check List and Related Systems by RSG-GAS Reactor Operators and Supervisors'. Non-routine maintenance activities on critical components of RSG-GAS include repair maintenance and in service inspections [16][17][18][19][20].…”

Section: Resultsmentioning

confidence: 99%

Evaluation on Structure, System, and Component Qualification in the Periodic Safety Review of RSG-GAS

Hastuti

Purwadi

Sudarmono

et al. 2023

Science and Technology Applications

View full text Add to dashboard Cite

In order to obtain license renewal for RSG-GAS operation expired in 2020, an evaluation on periodic safety review (PSR) should be performed as required by BAPETEN regulation. This PSR had been done from 2005 to 2015. The objectives of the qualification review is to ensure that the critical structure, system, and component (SSC) for safety fulfils the requirements. SSC, which is important to safety, is reviewed in term of its environment, service frequency, aging mechanism, aging mitigation, and aging degradation detection. The results of this detection are evaluated to achieve sustainable and safe operation and to identify SSC replacement and repair before a failure occurs. From the evaluation results, it can be concluded that SSC qualification during the period of 2005 – 2015 still fulfils the requirements so that safe and sustainable operation of RSG-GAS is assured.

show abstract

Improvement of Few-Group Homogenized Cross-Sections for RSG-GAS In-Core Fuel Management Code Batan-FUEL

Pinem

Hartanto

Hong

et al. 2023

Journal of Nuclear Engineering and Radiation Science

View full text Add to dashboard Cite

This paper presents the generation and the verification of the few-group homogenized cross-sections for Batan-Fuel. This code is routinely used for fuel management in the RSG-GAS. The Monte Carlo code Serpent 2 code, in conjunction with the latest nuclear data library ENDF/B-VIII.0, was used. Calculations using the existing newly generated few-group cross-section data were carried out for the 88th core. The calculated core parameters such as excess reactivity and control rod worth are compared to the available experimental data. On the other hand, the fuel burnup fraction and radial power peaking factor (PPF) are compared to the results of Serpent 2. It was shown that the new cross-section data have more consistency and a better agreement excess reactivity and control rod worth compared to the experimental data. Similarly, the U-235 burnup fraction and radial power peaking factor by the new cross-section data are also shown to concur well with Serpent 2. The newly generated few-group cross-sections are recommended to replace the existing ones for the fuel management of RSG-GAS.

show abstract

Evaluation of Equilibrium Core Operation of the RSG-Gas Reactor

Cited by 3 publications

References 8 publications

Effect of New Cross Section Data File on the Criticality of the RSG-GAS Research Reactor

Effect of New Cross Section Data File on the Criticality of the RSG-GAS Research Reactor

Evaluation on Structure, System, and Component Qualification in the Periodic Safety Review of RSG-GAS

Improvement of Few-Group Homogenized Cross-Sections for RSG-GAS In-Core Fuel Management Code Batan-FUEL

Contact Info

Product

Resources

About