Analisis beban (stress) sistem pipa pengendali volume dan kimiawi (CVS) pendingin reaktor pada PLTN AP600
Bambang Galung Susanto;
Ronnie Higuchi Rusli, supervisor; Darmadi Kusno, supervisor; Bambang Soegijono, examiner; Parangtopo Sutokusumo, examiner; Soehardjo Poertadji, examiner; Na, Peng Bo, examiner
(Universitas Indonesia, 1993)
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ABSTRACTThe stress analysis on the chemical and volume control piping system of the reactor coolant for the AP600 nuclear power plant has been done. By using CAEPIPE computer code version 3.32 revision 0, the first step of analysis has shown that CVS-APGOO piping system would be over stress if the piping supports were not used in the piping system. Furthermore the displacement of the piping system were larger and the piping would be deflected and /or ruptured. The second step of analysis has shown that the piping system would be in accordance with the limit stress of ASME Code Section III Subsection ND , 1980 Edition, providing the piping supports are placed in the proper location. In addition the displacement of the piping system would be very small, both on the nuclear power plant operation condition or during seismic event. Therefore, the CVS-APGOO piping system, that has been completed with the supports in the proper location is feasible to be fabricated and constructed. |
T6923-Bambang Galung Susanto.pdf :: Unduh
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No. Panggil : | T-Pdf |
Entri utama-Nama orang : | |
Entri tambahan-Nama orang : | |
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Subjek : | |
Penerbitan : | Depok: Universitas Indonesia, 1993 |
Program Studi : |
Bahasa : | ind |
Sumber Pengatalogan : | LibUI ind rda |
Tipe Konten : | text |
Tipe Media : | computer |
Tipe Carrier : | online resource |
Deskripsi Fisik : | vii, 150 pages ; 30 cm + appendix |
Naskah Ringkas : | |
Lembaga Pemilik : | Universitas Indonesia |
Lokasi : | Perpustakaan UI, Lantai 3 |
No. Panggil | No. Barkod | Ketersediaan |
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T-Pdf | 15-18-962437866 | TERSEDIA |
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