RADIOLOGICAL CHARACTERIZATION ANALYSIS OF GRAPHITE REFLECTOR FOR WASTE MANAGEMENT POLICY
<p>Radiological characterization analysis of graphite reflector for waste management policy has been studied.<br /> The Triga Mark II Reactor in Bandung was refurbished to 2000 kW power, and was commissioned at 2001. The<br /> refurbishing portion of the projects included disassemb...
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| Format: | Article NonPeerReviewed |
| Published: |
[Yogyakarta] : Fak. MIPA Universitas Gadjah Mada
2007
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| Online Access: | https://repository.ugm.ac.id/93992/ http://repository.ugm.ac.id/digitasi/index.php?module=cari_hasil_full&idbuku=1791 |
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| Institution: | Universitas Gadjah Mada |
| Summary: | <p>Radiological characterization analysis of graphite reflector for waste management policy has been studied.<br />
The Triga Mark II Reactor in Bandung was refurbished to 2000 kW power, and was commissioned at 2001. The<br />
refurbishing portion of the projects included disassembly of some components of the reactor core which have<br />
generated the contaminated materials, one of that was graphite reflector waste. In the paper discussed analysis of<br />
the radiological characterization of graphite reflector. The conclusions of the analysis shows that the dominant of<br />
radiological activated were Cs-137 produced from radiological contamination, Co-60 produced from radiological<br />
activation of stainless steel bolt and graphite, and C-14 produced from radiological activation of the graphite. The<br />
overall of dominant radiation level less than 100 years was Co-60 and after than 100 years was C-14. The result of<br />
analysis can be used to make management policy of the graphite reflector waste.</p> |
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