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EVALUASI PAPARAN RADIASI DI SEKITAR TANGKI PENUKAR BAHANG (HE) RSG-GAS

B. Bandriyana, BB and Pudjijanto MS, PMS (1999) EVALUASI PAPARAN RADIASI DI SEKITAR TANGKI PENUKAR BAHANG (HE) RSG-GAS. PROSIDING SEMINAR HASIL PENELITIAN PRSG. ISSN 0854-5278

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Abstract

EVALUASI PAPARAN RADIASI DI SEKITAR TANGKI PENUKAR BAHANG (HE) RSG-GAS. Pacta operasi reaktor dengan daya di alas 15 MW teramati adanya penyimpangan paparan radiasi di ruang sel primer dari harga perkiraan dalam desain. Berdasar keadaan ini dilakukan evaluasi paparan radiasi di sekitar pesawat penukar bahang yang berada di ruang sel primer dengan melakukan pengukuran dan perhitungan paparan radiasi serta evaluasi peralatan. Pengukuran paparan radiasi dilakukan dengan alat ukur portabel untuk 10titik tinjauan sedangkan pengamatan kontinyu dilakukan dari alat ukur terpasang UJA04 CRO02. Perhitungan teoritis paparan radiasi pacta daya reaktor 15 MW dilakukan berdasar teori pelemahan kernel dengan memperhitungkan pengaruh adanya udara yang terperangkap dalam tangki tunda. Hasil pengukuran paparan radiasi untuk 10 titik ukur di sekitar pesawat penukar bahang berkisar antara 2-40 mrem/jam. Hasil perhitungan paparan radiasi pacta satu titik ukur yang berjarak 3,7 m dari pesawat penukar bahang JEOI-BCOI dengan ketinggian 1,5 m dari grade besi untuk daya reaktor 15 MW adalah sebesar 16,23 fiR/jam. Pengamatan UJA04 . CRO02pacta awal dan akhir siklus operasi (dengan udara terperangkap dalam tangki tunda) menunjukan adanya kenaikan paparan radiasi. Dari evaluasi tersebut disimpulkan paparan radiasi di beberapa titik di sekitar pesawat penukar bahang melebihi paparan yang diperkirakan dalam SAR RSG-GAS (5 -10 mrem/jam) . ABSTRACT EVALUATION OF THE RADIATION EXPOSURE IN THE ENVOIRONMENT OF THE HEAT EXCHANGER. The radiation exposure data at primary cell when reactor operated on 15 MW was found higher than the design data. Based on this condition, an evaluation of radiation exposure on the entire of heat exchanger in the primary cell was carried out by measuring, and calculating the radiation exposure, observation of radiation exposure data and visual check of equipment. Measuring of radiation exposure was performed on 10 monitoring point by the portable equipment and assessing of radiation exposure data was performed base on the data of UJA04 CRO02. Calculating of radiation exposure was performed on the 15 MW power reactor operation based on kernel theory and air volume escaped in the delay chamber. Observation of UJA04 CRO02 on the early and the end of reactor operation cycle showed the radiation exposure increase. The result of radiation exposure measuring on 10 monitoring point are 2-40 mrem/hour, the calculating result at the location of 3.7 m from the heat exchanger JEOI BCOI and 1.5 level from the grade are 16.23 mrem/hour. This evaluation concluded that some of the radiation exposure rate in the entire of heat exchanger are higher than the expected value from SAR (5-10 mrem/hour).

Item Type: Article
Subjects: Reaktor Nuklir > Teknologi Reaktor > Fisika Reaktor
Divisions: Pusat Reaktor Serba Guna
Depositing User: EDITOR PRSG BATAN
Date Deposited: 20 Sep 2018 03:31
Last Modified: 20 Sep 2018 03:31
URI: http://repo-nkm.batan.go.id/id/eprint/3980

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