ANALISIS OPTIMASI TARGET U-235 PENGKAYAAN RENDAH (LEU) UNTUK MENDUKUNG PRODUKSI 99Mo DAN TARGET BATU TOPAZ DI REAKTOR RSG-GAS

Sutrisno, Sutrisno; Ratnawati, Elisabeth; Susanti, Fitri

doi:10.17146/gnd.2018.21.1.3946

Cited by 3 publications

(5 citation statements)

References 10 publications

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“…The maximum number of target LEU electroplating in the CIP position is 36 g. Reactivity change due to target irradiation is 597.724 pcm.This result is still below the specified limit of 2000 pcm. Compared with target LEU foil [6], the number of irradiated targets in CIP was 108 g with reactivity change of 1179.545 pcm.…”

Section: Resultsmentioning

confidence: 99%

“…-Excess reactivity change for with and without target, %Δk/k -Radial power peaking factor -Axial power peaking factor as a function of control rod insertion -The power peaking factor at the target Although the target mass is relatively small compared to the uranium mass, it can give a strong effect if the macroscopic cross-section of the neutron absorption is large. Since the capsule are modeled in 3-deminsional, axially, it is expected the calculated result is better than 2-dimensional calculations [6].…”

Section: Cell and Core Calculationsmentioning

confidence: 92%

“…Studies in optimizing the irradiation target in the research reactor have been carried out, so the reactor operation to be more economic [2][3][4]. For RSG-GAS reactor, the similar studies have been carried out, further, specifically to the single or multi targets [5,6]. All studies are focused on the 99 Mo radionuclide production since there are many request form the local or domestic market.…”

Section: Sg-gas (Reaktor Serba Guna-ga Siwabessy) Is a Multi-purpose Reactor Based On The Open Pool Mtr (Materials Testingmentioning

confidence: 99%

“…The study on the optimum LEU electroplating target has been carried out in Ref. [6]. However, the LEU target is combined with the gemstone target that inserted in the IPs core grid position.…”

Section: Sg-gas (Reaktor Serba Guna-ga Siwabessy) Is a Multi-purpose Reactor Based On The Open Pool Mtr (Materials Testingmentioning

confidence: 99%

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Neutronic Analysis on Irradiation of the Leu Electroplating Target in the RSG-Gas Reactor for Production of 99mo Radionuclide

Pinem

Sembiring²,

Tukiran³

et al. 2018

gnd

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Neutronic analysis on irradiation of the LEU electroplating target in the RSG-GAS reactor for production of 99 Mo radionuclide. RSG-GAS reactor is a research reactor operated for radioisotope production, neutron activation analysis, research material testing, industry demand, R & D institutions and universities. The irradiation of the LEU target on the reactor core to produce 99 Mo radioisotope is one of the routine activities of RSG-GAS reactor operation. The target insertion in the core will change the neutronic characteristic of the core so it can exceed the safety limits of reactor operation. The neutronic parameters due to the insertion of the LEU electroplating target into the reactor core irradiation facility is analyzed in this paper. The neutronic parameters for optimizing the LEU electroplating irradiated target are important for the safety of the reactor operation. Neutronic parameter calculations were performed using WIMS/D5 and Batan-3DIFF codes routinely used for RSG-GAS core calculations. Based on calculations irradiating the LEU electroplating target in a CIP irradiation position of 36 g causes a reactivity change of 597.724 pcm and a maximum radial power peaking factor of 1.3078. The values are within the limits permitted for the safety of the reactor operation i.e. the maximum reactivity change and radial power peaking factor of 2000 pcm and 1.4, respectively.

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Section: Resultsmentioning

confidence: 99%

Section: Cell and Core Calculationsmentioning

confidence: 92%

Section: Sg-gas (Reaktor Serba Guna-ga Siwabessy) Is a Multi-purpose Reactor Based On The Open Pool Mtr (Materials Testingmentioning

confidence: 99%

Section: Sg-gas (Reaktor Serba Guna-ga Siwabessy) Is a Multi-purpose Reactor Based On The Open Pool Mtr (Materials Testingmentioning

confidence: 99%

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Neutronic Analysis on Irradiation of the Leu Electroplating Target in the RSG-Gas Reactor for Production of 99mo Radionuclide

Pinem

Sembiring²,

Tukiran³

et al. 2018

gnd

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“…Selain itu didalam teras ada 5 fasilitas sistem rabbit, tujuh elemen reflektor berilium memiliki lubang berdiameter 50 mm dan dapat digunakan sebagai fasilitas iradiasi reflektor atau diisi dengan berilium bila tidak digunakan [3]. Fasilitas iradiasi dalam teras reaktor digunakan untuk produksi radioisotop, batu topaz, analisis aktivasi neutron, permintaan dari industri, lembaga litbang dan universitas [4]- [6]. Selain fasilitas iradiasi dalam teras, reaktor RSG-GAS mempunyai 6 tabung berkas neutron yang digunakan untuk penelitian dan fasilitas silicon doping serta fasilitas power ramp test facility (PRTF).…”

Section: Fasilitas Iradiasiunclassified

Kajian Penambahan Dummy Aluminum Pada Posisi Iradiasi Sentral (Cip) Terhadap Parameter Neutronik Reaktor RSG-Gas

Susanto¹,

Susanti²

2019

bprn

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KAJIAN PENAMBAHAN DUMMY ALUMINIUM PADA POSISI IRADIASI SENTRAL (CIP) TERHADAP PARAMETER NEUTRONIK REAKTOR RSG-GAS. Reaktor RSG-GAS adalah reaktor riset yang dioperasikan untuk keperluan produksi radioisotop, analisis aktivasi neutron, penelitian dan uji material. Reaktor RSG-GAS beroperasi dengan rata-rata energi terbangkitkan sebesar 625 MWd setiap siklus dan manajemen bahan bakar teras menggunakan pola 5/1 untuk pemuatan bahan bakar. Setiap pergantian teras dilakukan perhitungan dan pengukuran parameter reaktor untuk mengetahui pengaruh terhadap keselamatan operasi reaktor. Pada kondisi operasi normal fasilitas iradiasi dalam teras berisi air atau dummy aluminium. Penambahan dummy aluminium pada fasilitas iradiasi perlu diketahui pengaruhnya terhadap parameter neutronik reaktor RSG-GAS. Tujuan penulisan makalah ini yaitu melakukan perhitungan dan pengukuran parameter operasi reaktor dan mengetahui pengaruh penambahan dummy aluminium terhadap reaktivitas dan fluks neutron pada teras 97 reaktor RSG-GAS. Perhitungan parameter operasi dilakukan menggunakan kombinasi program WIMS/D5 untuk generasi tampang lintang sel, Batan-2DIFF untuk menghitung reaktivitas dan faktor puncak daya radial serta Batan-3DIFF untuk menghitung faktor puncak daya aksial dan fluks neutron dalam teras reaktor. Efek reaktivitas akibat penempatan dummy aluminium pada CIP sebesar 0,17 %Δk/k. Jika dummy aluminium diletakkan di CIP dan IP akan menaikkan fluks di posisi tersebut karena aluminium mempunyai daya moderasi yang sangat baik. Nilai faktor puncak daya radial dan aksial masing-masing 1,2200 dan 1,2902. Berdasarkan hasil perhitungan dan pengukuran besaran tersebut masih berada dalam batas yang diizinkan untuk keselamatan operasi reaktor dan menunjukan bahwa teras 97 reaktor RSG-GAS memenuhi batas keselamatan operasi reaktor.Kata kunci: Dummy aluminium, reaktivitas, fasilitas iradiasi, operasi reaktor

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Safety analysis of the irradiation of Tellurium (Te) target in G.A. Siwabessy Reactor

Sutrisno

Hakim

Purwadi

2020

J. Phys.: Conf. Ser.

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Safety Analysis of the Irradiation of Tellurium (Te) Target in G.A. Siwabessy Reactor. Providing public service becomes one of the priority programs made by the Head of BATAN, such a program is the radioisotope production of Iodine 131 (I-131), which emits gamma and beta that are utilized for medical purpose. The radioisotope can be produced by irradiating the target of Tellurium dioxide (TeO2) on the G.A. Siwabessy Reactor core. Tellurium dioxide (TeO2) is irradiated on the position of Central Irradiation Position (CIP) D-6 and E-7 because the Irradiation Position (IP) is used for Topaz irradiation and CIP (D-6, E-7) is used for the irradiation of Low Enriched Uranium (LEU). Based on the several safety requirements such as analyze the optimum amount of the Tellurium target on CIP (D-6, E-7) with Topaz and LEU. The scope of the research includes the reactivity disturbance, radial power peaking factor and thermohydraulic disturbance. The diffusion group constant of the model uses the program of WIMSD-5B and the result is used for calculating reactivity disturbance and radial power peaking factor with the program package of BATAN-2DIFF. The thermohydraulic disturbance is calculated with using the Generalized Gap Temperature Calculation (GENGTC) program. The calculation of the reactivity of 750 gram (6x125 gram) Tellurium is resulting the change of negative reactivity of-0.27% Δk/k and the value of radial power peaking factor is 1.34 and the temperature at the center of TeO2 target is 366.7°C and outside the capsule (Aluminum) is 58.39°C, if it is compared to the safety margin of ± 2% Δk/k, PPFrad max=2.6, melting point of Al=660°C, melting point of Te=449.5°C, so all the parameters still meets the safety requirement.

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ANALISIS OPTIMASI TARGET U-235 PENGKAYAAN RENDAH (LEU) UNTUK MENDUKUNG PRODUKSI 99Mo DAN TARGET BATU TOPAZ DI REAKTOR RSG-GAS

Abstract: ABSTRAK ANALISIS OPTIMASI TARGET 235 U PENGKAYAAN RENDAH (LEU) UNTUK MENDUKUNG PRODUKSI 99 Mo DAN TARGET BATU TOPAZ DI REAKTOR RSG-GAS. Peningkatan utilitas produksi radioisotop di reaktor RSG-GAS

Cited by 3 publications

References 10 publications

Neutronic Analysis on Irradiation of the Leu Electroplating Target in the RSG-Gas Reactor for Production of 99mo Radionuclide

Neutronic Analysis on Irradiation of the Leu Electroplating Target in the RSG-Gas Reactor for Production of 99mo Radionuclide

Kajian Penambahan Dummy Aluminum Pada Posisi Iradiasi Sentral (Cip) Terhadap Parameter Neutronik Reaktor RSG-Gas

Safety analysis of the irradiation of Tellurium (Te) target in G.A. Siwabessy Reactor

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