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VERIFIKASI DESAIN TERMOHIDROLIKA TERAS PWR KELAS 1000 MWe

Muhammad Darwis Isnaini, MDI and Pudjianto, pjt (2009) VERIFIKASI DESAIN TERMOHIDROLIKA TERAS PWR KELAS 1000 MWe. VERIFIKASI DESAIN TERMOHIDROLIKA TERAS PWR KELAS 1000 MWe. pp. 33-39. ISSN 0854 - 2910

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Abstract

ABSTRAK VERIFIKASI DESAIN TERMOHIDROLIKA TERAS PWR KELAS 1000 MWe. Telah dilakukan verifikasi desain termohidrolika teras PLTN jenis PWR kelas 1000 MWe (daya listrik terbangkit berkisar antara 900 sampai 1.100 MWe). Latar belakang penelitian ini adalah belum adanya suatu keputusan tentang jenis PLTN apa yang akan dipilih, salah satunya adalah karena kurangnya data teknis yang dimiliki tentang karakteristika PLTN yang terpublikasi secara luas. Oleh sebab itu dilakukan suatu verifikasi dengan batasan dipilih PLTN jenis PWR, dengan tujuan membandingkan karakteristika termohidrolika PWR, agar hasilnya dapat dipakai sebagai bahan masukan dalam memutuskan jenis PLTN yang akan dipilih. Verifikasi dilakukan untuk teras PWR generasi II (PWR G2) buatan Mitsubishi yang terdiri atas 157 perangkat elemen bakar dengan daya 2.660 MWt dan teras PWR Tipikal buatan Westinghouse yang terdiri atas 193 perangkat elemen bakar dengan daya 3.411 MWt. Perhitungan dilakukan dengan menggunakan program THAL (Thermal Hydraulics Assigned for LWR) yaitu program yang dipakai untuk perhitungan termohidrolika teras pada reaktor daya jenis air ringan, baik BWR maupun PWR. Program ini dapat dipakai untuk perhitungan satu batang bahan bakar atau satu perangkat bahan bakar atau satu teras sekaligus. Hasil verifikasi desain PWR G2 Mitsubishi untuk daya 2.660 MWt dengan laju alir 45.400 ton/jam dan suhu pendingin masukan 288o C menunjukkan suhu keluaran 340o C (perbedaan 4,62%), suhu maksimum pelat dan tengah meat masing-masing sebesar 360,71o C dan 1.943,83o C, serta marjin keselamatan DNBR minimum 2,15. Adapun verifikasi desain PWR Tipikal Westinghouse untuk daya 3.411 MWt dengan laju alir 60.000 ton/jam dan suhu pendingin masukan 292,6o C menunjukkan suhu keluaran 344,7o C (perbedaan 4,78%), suhu maksimum pelat dan tengah meat masing-masing sebesar 372,17o C dan 2.037,06o C, serta marjin keselamatan DNBR minimum 1,45. Dibandingkan dengan batas suhu maksiumum meat agar tidak terjadi pelelehan yang nilaninya 2.594o C dan marjin keselamatan DNBR minimum sebesar 1,24, maka kedua PLTN jenis PWR tersebut dapat dioperasikan dengan selamat. Meskipun hasil perhitungan masih cukup kasar, program ini dapat memberikan gambaran tentang distribusi aksial suhu pendingin, kelongsong dan meat bahan bakar, serta margin keselamatan DNBR. Kata kunci : Verifikasi desain termohidrolika, PWR G2, PWR Tipikal. ABSTRACT VERIFICATION OF THERMAL-HYDRAULIC DESIGN OF PWR CORE 1000 MWe CLASS. Verification of thermal-hydraulics design of PWR core 1000 MWe class (reactor power of 900 – 1,100 MWe) was carried out. The reasoning of this research is, the decision of nuclear power plant (NPP) type has not been selected yet, because there were not enough technical data about any kinds of NPP’s characteristics owned. Therefore, a verification was carried out, constraint for PWR type only, by the objective, comparing the PWR’s thermal-hydraulic characteristics, in order that the result be usable as opinion input in deciding what NPP’s type will be selected. Verifications were carried out for two types of PWR, i.e., PWR 2nd Generation (PWR G2) made by Mitsubishi that contains of 157 fuel element assemblies for 2,660 MWt and Typical PWR that made by Westinghouse that contains of 193 fuel element assemblies for 3,411 MWt. The calculations were performed using THAL program (Thermal- Hydraulics Assigned for LWR) in which the program is useful for thermal-hydraulics calculation in light water typed reactor of BWR or PWR. The program is capable of calculation of one fuel rod or one fuel assembly or one core in time. For reactor power of 2,660 MWt with flow rate of 45,400 ton/h and inlet temperature of 288°C, the verification result of 34 Mitsubishi PWR G2 design shows that outlet temperature is 340°C (different is 4.62%), maximum cladding temperature and meat temperature are 360.71o C and 1,943.83o C, and the safety margin for DNBR is 2.15. Whereas the verification result for Westinghouse Typical PWR design for reactor power of 3,411 MWt with flowrate 60,000 ton/h and inlet temperature 292.6o C shows that the outlet temperature is 344.7o C, the maximum cladding and meat temperature are 372.17°C and 2,036.06°C, and safety margin for DNBR is 1.45. Referring to the maximum meat temperature limit is 2,594°C to avoid fuel melting and safety margin for DNBR is 1.24, both PWR typed nuclear power plant can be operated safely. Even the calculation used global inputs of one fuel assembly, the program results axial temperature distribution for coolant, cladding, and fuel meat including safety margin of DNBR as well. Keywords: Verification of thermal-hydraulics design, PWR 2nd Generation, PWR Typical.

Item Type: Article
Subjects: Keselamatan dan Keamanan Nuklir
Divisions: Pusat Teknologi dan Keselamatan Reaktor Nuklir
Depositing User: USER PTKRN BATAN
Date Deposited: 09 Nov 2018 08:38
Last Modified: 09 Nov 2018 08:38
URI: http://repo-nkm.batan.go.id/id/eprint/4853

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