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"Petugas shift merupakan bagian dari pekerja kritis di Instalasi RSG-GAS. Sistem kerja shift dan tuntutan kerja yang kompleks di instalasi nuklir menyebabkan petugas shift rentan mengalami kelelahan kerja. Kelelahan kerja memiliki kontribusi terhadap penurunan performa kerja, penurunan konsentrasi, penurunan pemenuhan prosedur maupun penurunan kewaspadaan. Penelitian ini bertujuan untuk mengevaluasi tingkat kelelahan kerja petugas shift dan melakukan analisis terhadap faktor risiko yang berkontribusi pada kelelahan kerja petugas shift di RSG-GAS Tahun 2022. Desain penelitian adalah cross-sectional. Instrumen yang digunakan dalam penelitian ini adalah kuesioner, alat ukur lingkungan kerja, wawancara, dan telaah dokumen. Metode analisis menggunakan analisis deskriptif dan inferensial dengan uji korelasi. Hasil penelitian menunjukkan seluruh petugas shift mengalami kelelahan dengan tingkat kelelahan ringan sebesar 31,25%, kelelahan sedang sebesar 64,58%, dan kelelahan berat sebesar 4,17%. Faktor risiko kelelahan kerja adalah status Gizi yang diukur dengan indeks massa tubuh, kualitas tidur, beban kerja, dan desain tugas. Faktor risiko kelelahan umum adalah indeks massa tubuh, kualitas tidur, kuantitas tidur, konsumsi kafein, beban kerja, dan desain tugas. Faktor risiko kelelahan fisik adalah usia, kualitas tidur, kuantitas tidur, masa kerja, posisi kerja, beban kerja, desain tugas, dan tekanan udara negatif. Faktor risiko pelemahan aktivitas adalah kepuasan kerja. Faktor risiko pelemahan motivasi adalah kualitas tidur, kuantitas tidur, desain tugas dan shift malam. Faktor risiko kelelahan mental adalah kualitas tidur, beban kerja, desain tugas, pencahayaan, dan tekanan udara negatif. Rekomendasi pengendalian melibatkan manajemen dan petugas shift dengan mengembangkan program manajemen kelelahan kerja sesuai kondisi di Instalasi Nuklir.......Shift workers are part of critical workers at the RSG GAS Installation. The shift work system and complex work demands in nuclear installations cause shift workers to be prone to work fatigue. Work fatigue has contributed to decreased work performance, decreased concentration, decreased in procedure compliance, and reduced alertness. This study aims to evaluate the level of work fatigue of shift workers and analyze the risk factors that contribute to the work fatigue of shift workers at RSG-GAS in 2022. This research is a quantitative descriptive study with a cross-sectional design. The instruments used in this research are questionnaires, measuring tools for the environment, interviews, and documents. The method of analysis in this research is descriptive and inferential analysis with a correlation test. The results showed that all shift workers experienced fatigue with mild fatigue level of 31,25%, moderate fatigue of 64,58%, and severe fatigue of 4,17%. The risk factors for work fatigue (total score) are nutritional status as measured by body mass index, sleep quality, workload and task design. The risk factors for general fatigue are body mass index, sleep quality, sleep quantity, caffeine consumption, workload, and task design. The risk factors for physical fatigue are age, sleep quality, sleep quantity, years of service, job role, workload, task design, and negative air pressure. The risk factor for reduced activity is job satisfaction. The risk factors for reduced motivation are sleep quality, sleep quantity, task design, and night shift. The risk factors for mental fatigue are sleep quality, workload, task design, lighting, and negative air pressure. Control recommendations involve management and shift worker by developing a work fatigue management program according to the conditions at the Nuclear Installation."

"Research of UMo fuel for research reactor has been developing right now. The fuel of research reactor used is uranium low enrichment with high density. For supporting the development of fuel, an assessment of mini fuel in the RSG-GAS core was performed. The mini fuel are U7Mo-Al and U6Zr-Al with densitis of 7.0gU/cc and 5.2 gU/cc, respectively. The size of both fuel are the same namely 630x70.75x1.30 mm were inserted to the 3 plates of dummy fuel. Before being irradiated in the core, a calculation for safety analysis from neutronics and thermohydrolics aspects were required. However, in this paper will discuss safety analysis of the U7Mo-Al and U6Zr-Al mini fuels from neutronic point of view. The calculation was done using WIMSD-5B and Batan-3DIFF code. The result showed that both of the mini fuels could be irradiated in the RSG-GAS core with burn up less than 70 % within 12 cycles of operation without over limiting the safety margin. Power density of U7Mo-Al mini fuel bigger than U6Zr-Al fuel."

"Reaktor Serba Guna GA. Siwabessy RSG-GAS menyimpan potensi bahaya radiasi, walaupun telah didesain dan dibangun dengan mempertimbangkan berbagai faktor keselamatan. Sistem keselamatan pada pendingin primer merupakan komponen yang penting dan berfungsi sebagai penghalang ganda reaktor nuklir. Apabila sistem pendingin primer gagal beroperasi, maka sistem keselamatan pada sistem pendingin primer akan bekerja untuk mencegah pelepasan zat radioaktif, melalui sistem 'scram', sehingga reaktor dapat terhindar dari kecelakaan yang parah. Oleh karena itu, evaluasi sistem keselamatan dari sistem pendingin primer, dengan menggunakan suatu metode analisis keselamatan yang tepat, perlu dilakukan untuk mengukur tingkat kinerja dari sistem keselamatan tersebut. Fault tree analysis sering digunakan secara deduktif untuk mengevaluasi kinerja keselamatan secara probabilistik probabilistic safety assessment, PSA . Dalam melakukan PSA ini digunakan data generik karena data kegagalan komponen yang dimiliki oleh suatu objek analisis biasanya tidak tersedia secara detail. Data generik tidak menggambarkan kondisi kebolehjadian kegagalan komponen yang sebenarnya. Selain itu, data generik tidak cocok untuk diterapkan pada komponen ndash; komponen yang sudah mengalami proses ageing karena adanya penurunan keandalan komponen yang diakibatkan pada proses ageing. Penggunaan data generik akan menambah ketidakpastian pada hasil PSA. Untuk mengatasi hal tersebut diusulkan penggunaan metode fuzzy fault tree analysis FFTA. Nilai probabilitas basic events yang dihasilkan dari FFTA kemudian digunakan untuk menghitung probabilitas kejadian menggunakan metode Event Tree Analysis ETA dan diperoleh hasil probabilitas kejadian dengan nilai terbesar 4,304 x 10-8/tahun. Seluruh skenario berdasarkan CDF dan CDS, berada dalam kategori medium risk dan low risk, sehingga dapat dinyatakan bahwa RSG ndash; GAS aman untuk dioperasikan. ......G.A. Siwabessy Multipurpose Reactor RSG GAS has significant potency of radiation hazard, although it has been designed and constructed by considering comprehensive safety factors. The safety system of primary cooling system is one of the most important components of the reactor and serve as multiple barriers in a nuclear reactor. If there is a failure on the primary cooling system operation, the safety system in the primary cooling system will work to prevent the release of radioactive material through the ldquo scram rdquo system, a severe accident of the reactor can be avoided. Therefore, an evaluation toward the safety system of the primary cooling system by occupying the proper safety analysis method, is required to be carried out. So that, the performance level of the safety system can be figured out. Fault tree analysis is frequently applied to deductively carry out the safety system evaluation by occupying the probabilistic assessment method PSA . To perform this PSA, the generic data is used because the data of components failure owned by an object of analysis, is not available in detail. The generic data used in the safety analysis does not describe the real probability of component failures. In addition, generic data is not applicable for old components because the old components reliability is really affected by the ageing process. But, when generic data is occupied on PSA then, it will increase the uncertainty value of the PSA result. To solve this problem, another safety analysis method, called as Fuzzy Fault Tree Analysis FFTA Method, is proposed in this research. The basic event probability values generated from FFTA are then applied for calculating the probability of event using Event Tree Analysis ETA Method in order to obtain the probability of each event, with the result that, the obtained greatest value is 4.304 x 10 8 year. All scenario based on CDF and CDS are in the medium risk and low risk category, so it can be concluded that RSG GAS is safe to be operated."

"Badan Tenaga Nuklir Nasional BATAN sebagai institusi di Indonesia yang mengurusi pengaplikasian energi nuklir untuk Indonesia telah mengoperasionalkan RSG 30Mwatt di Kawasan Puspitek Serpong sejak tahun 1987. Reaktor ini berpotensi melepaskan radiasi dari unsur-unsur radioaktif dari hasil reaksi fisi unsur tersebut. Potensi cemaran ini dikhawatirkan dapat mengganggu keseimbangan dan kesehatan lingkungan sekitar, khususnya lingkungan perariran terdekat seperti Sungai Cisadane. Beberapa radionuklida antropogenik seperti 137Cs sulit terdeteksi sehingga diperlukan adanya metode evaluasi kualitas lingkungan berdasarkan analisisnya tehadap jaringan molekul suatu organisme yang terpapar radionuklida tersebut, metode ini disebut Biomonitoring. Pada penelitian ini dilakukan eksperimen biokinetik dengan penentuan nilai Faktor Konsentrasi CF dan Faktor Biokonsentrasi BCF radionuklida 137Cs oleh Ikan Mas Cyprinus carpio melalui jalur air tawar yang dipengaruhi oleh kondisi lingkungan akuatiknya , yaitu konsentrasi Ion Kalium K Percobaan dilakukan melalui tiga tahapan, yaitu akumulasi/pengambilan, depurasi/pelepasan dan pembedahan organ. Hasil penelitian menunjukkan kenaikan konsentrasi K dalam media menurunkan nilai CF pada Cyprinus carpio. Nilai faktor konsentrasi CF 137Cs oleh Cyprinus carpio setelah akhir akumulasi dalam kondisi media dengan variasi konsentrasi Kalium 2,5 ; 5 ;7,5 ; dan 10 ppm berturut ndash; turut adalah 2,762 ; 2,645 ; 2,637 ; 2,586 ml.g-1 dan nilai Faktor Biokonsentrasi BCF variasi konsentrasi ion K 2,5 ; 5 ; 7,5 ; dan 10 ppm berturut-turut adalah 1,32 ; 2,12 ; 1,77 ; 2,07 ml.g-1. Berdasarkan nilai-nilai tersebut , Ikan Mas Cyprinus carpio dapat dikategorikan sebagai bioindikator dari 137Cs.

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Badan Tenaga Nuklir Nasional BATAN as an institution in Indonesia that developed nuclear energy in Indonesia has operated RSG 30 MWatt in Puspitek Serpong Area since 1987. This reactor has the potential to emit radiation from radioactive elements produced by fission reaction of the elements. The environmental hazard potential is feared to disrupt the balance and health of surrounding environment, especially the nearby waters like Cisadane River. Few anthropogenic radionuclides like 137Cs are difficult to detect that the need for a method to evaluate environment quality based on molecular network of an organism exposed to the radionuclide arises, and the said method is called Biomonitoring. In this study biokinetic experiment is conducted with determination of Concentration Factor CF and Bioaccumulation Factor values of 137Cs by Goldfish Cyprinus carpio by means of freshwater influenced by its aquatic environment condition, which is Potassium ion concentration K . This test is conducted through three steps, which is accumulation sampling, depuration release, and organ dissection. The results of the tests showed the increase of K concentration in the medium decrease CF value of Cyprinus carpio. CF value of 137Cs concentration by Cyprinus carpio after the end accumulation in media conditioned with variation of Potassium concentration 2.5 5 7.5 and 10 ppm respectively are 2.762 2.645 2.637 2.568 ml.g 1 and Bioconcentration Factor BCF for variation of K ion concentration 2.5 5 7.5 and 10 ppm respectively are 1.32 2.12 1.77 2.07 ml.g 1. Based on those values, Goldfish Cyprinus carpio can be categorized as bioindicator for 137Cs. "