Neutronic simulation of CAREM-25 small modular reactor

Tashakor, S.; Zarifi, Ehsan; Naminazari, M.

doi:10.1016/j.pnucene.2017.05.016

Cited by 10 publications

(4 citation statements)

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“…The coolant used can be light water, heavy water, gas, or liquid metal. For example, in pressurized water reactor (PWR), the light water in the primary cooling system is kept under pressure to prevent it from boiling and flowing through the reactor core [9]. While most reactor uses water in their cooling system, some reactors use other alternative such as gas and liquid metal as their primary coolant.…”

Section: Materials and Methods 21 Nuclear Reactor Cooling Systemmentioning

confidence: 99%

A review on predictive maintenance technique for nuclear reactor cooling system using machine learning and augmented reality

Nor

Kassim

Minhat

et al. 2022

IJECE

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<span lang="EN-US">Reactor TRIGA PUSPATI (RTP) is the only research nuclear reactor in Malaysia. Maintenance of RTP is crucial which affects its safety and reliability. Currently, RTP maintenance strategies used corrective and preventative which involved many sensors and equipment conditions. The existing preventive maintenance method takes a longer time to complete the entire system’s maintenance inspection. This study has investigated new predictive maintenance techniques for developing RTP predictive maintenance for primary cooling systems using machine learning (ML) and augmented reality (AR). Fifty papers from recent referred publications in the nuclear areas were reviewed and compared. Detailed comparison of ML techniques, parameters involved in the coolant system and AR design techniques were done. Multiclass support vector machines (SVMs), artificial neural network (ANN), long short-term memory (LSTM), feed forward back propagation (</span><span lang="EN-US">FFBP), graph neural networks-feed forward back propagation (GNN-FFBP) and ANN were used for the machine learning techniques for the nuclear reactor. Temperature, water flow, and water pressure were crucial parameters used in monitoring a nuclear reactor. Image marker-based techniques were mainly used by smart glass view and handheld devices. A switch knob with handle switch, pipe valve and machine feature were used for object detection in AR markerless technique. This study is significant and found seven recent papers closely related to the development of predictive maintenance for a research nuclear reactor in Malaysia.</span>

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Section: Materials and Methods 21 Nuclear Reactor Cooling Systemmentioning

confidence: 99%

A review on predictive maintenance technique for nuclear reactor cooling system using machine learning and augmented reality

Nor

Kassim

Minhat

et al. 2022

IJECE

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“…aket program WIMSD-5B [1] dan CITATION [2] adalah paket program yang banyak digunakan untuk perhitungan sel dan teras reaktor. Akurasi kombinasi WIMSD-5B/CITATION dalam perhitungan kritikalitas atau parameter neutronik teras untuk berbagai jenis reaktor telah banyak dipublikasikan [3][4][5][6]. Namun demikian, kombinasi kedua paket program ini belum pernah digunakan untuk reaktor jenis Molten Salt Reactor (MSR).…”

Section: Pendahuluanunclassified

Analisis Akurasi Paket Program Wimsd-5b/Citation Dalam Perhitungan Kritikalitas Reaktor Msre Accuration Analysis of the Wimsd-5b/Citation Codes on the Criticality Calculation of the Msre Reactor

Permana

Tamaza²,

Sid'qon³

2021

gnd

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Paket program WIMSD-5B/CITATION telah digunakan sebagai perangkat analitik kekritisan berbagai jenis reaktor dan memberikan hasil yang memuaskan. Meskipun demikian, paket program ini belum pernah digunakan untuk menganalisis kekritisan reaktor jenis MSR (Molten Salt Reactor). Dalam penelitian ini program WIMSD-5B/CITATION dianalisis akurasinya untuk menghitung kritikalitas reaktor MSRE (Molten Salt Reactor Experiment), yaitu reaktor MSR yang pernah dioperasikan sebagai fasilitas eksperimen. Tujuan penelitian ini adalah untuk mengetahui akurasi WIMSD-5B/CITATION untuk menghitung kritikalitas bahan bakar Tipe C di reaktor MSRE. Kritikalitas teras reaktor MSRE dihitung dengan 6 kelompok energi neutron dengan model geometri R-Z. Hasil perhitungan menunjukkan model sel yang menempatkan celah di tengah grafit (Model 1) lebih baik dibanding dengan sel yang menempatkan celah bahan bakar di luar grafit (Model 2). Namun demikian perbedaan relatif antara hasil perhitungan dan n hasil eksperimen masih tinggi yaitu 7,23%. Akurasi perhitungan kritikalitas didominasi oleh faktor model geometri sel dan teras. Pengaruh signifikan juga bersumber dari data jumlah void dan komposisi pengotor Li-6. Hasil penelitian juga menunjukkan bahwa fluks neutron dan faktor puncak daya radial di teras MSRE sangat sensitif terhadap model sel bahan bakar.

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“…The RSG-GAS core control rod contains a material that highly absorbs neutrons, so that the presence of the control rod will affect the significant neutron flux value in the reactor core irradiation facility. This flux change will basically change the reactivity value of the existing control rods, so that the number of individual control rod values can be significantly different from the collective number [5]. This difference is due to the interaction effect between control rods.…”

Section: Introduction mentioning

confidence: 99%

Analyses of Neutron Absorber Materials on the Safety Parameters in the RSG-Gas Reactor

Suparlina

Surbakti²,

Pinem³

et al. 2021

Tri Dasa Mega

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Shutdown system in RSG-GAS reactor is using neutron absorber. There are 3 kinds of absorber material in research reactors including Ag-In-Cd alloy, B4C, and Hf. In this works, analyses of different neutron absorbers on the main safety core parameters in the RSG-GAS research reactor are selected for analyses. Their integral effects on the main neutronic core parameters important to safety issues are investigated. These parameters are core excess reactivity, shutdown margin, total reactivity worth of control rods, PPF and neutron flux . The RSG-GAS core silicide fuel is selected as the case study to verify calculations. A three-dimensional, four-group diffusion model is selected for core calculations. The well-known WIMSD-5B and Batan-3DIFF reactor codes are used to carry out these calculations. It is found that the largest shutdown margin is gained using the B4C; also the lowest PPF is gained using the Hf material. The maximum point power densities belong to the inside fuel regions surrounding the CIP (centre irradiation position), surrounded by control fuel elements, and the peripheral fuel elements beside the berrylium reflector. The greatest and least fluctuation of the point power densities are gained by using B4C and Ag-In-Cd alloy, respectively.

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Neutronic simulation of CAREM-25 small modular reactor

Cited by 10 publications

References 0 publications

A review on predictive maintenance technique for nuclear reactor cooling system using machine learning and augmented reality

A review on predictive maintenance technique for nuclear reactor cooling system using machine learning and augmented reality

Analisis Akurasi Paket Program Wimsd-5b/Citation Dalam Perhitungan Kritikalitas Reaktor Msre Accuration Analysis of the Wimsd-5b/Citation Codes on the Criticality Calculation of the Msre Reactor

Analyses of Neutron Absorber Materials on the Safety Parameters in the RSG-Gas Reactor

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