Sri Bawani, 1117041043 (2015) DESAIN REAKTOR AIR SUPERKRITIS (SUPERCRITICAL COOLED WATER REACTOR) DENGAN MENGGUNAKAN BAHAN BAKAR URANIUM-THORIUM MODEL TERAS SILINDER. FAKULTAS MATEMATIKA DAN ILMU PENGETAHUAN ALAM, UNIVERSITAS LAMPUNG.
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Abstrak (Berisi Bastraknya saja, Judul dan Nama Tidak Boleh di Masukan)
Telah dilakukan penelitian desain reaktor air superkritis (SCWR) dengan bahan bakar uranium-thorium model teras silinder. Reaktor didesain untuk menghasilkan daya termal yang maksimal dan kondisi kritis. Parameter yang dianalisis pada penelitian ini adalah fraksi volume, densitas atom, pengayaan bahan bakar U-235, ukuran teras reaktor, kekritisan, dan distribusi rapat daya. Analisis reaktor dengan teras yang berbentuk silinder dua dimensi (x,y) pada 1/6 bagian teras dengan menggunakan CITATION pada SRAC. Pada penelitian ini bahan bakar yang digunakan U-235 dan Th-232, stainless steel sebagai selongsong, air ringan sebagai moderator dan pendingin. Sehigga diperoleh desain teras reaktor yang ideal dengan ukuran kolom (x) = 340 cm dan baris (y) = 170 cm. Pengayaan pada bagian pertama bahan bakar 3,1704%, bagian kedua 2,5% dan bagian ketiga 4%. Desain ini menghasilkan daya termal 1000 M Wth, rapat daya maksimal sebesar 114,4073 watt/cm3 dan nilai k-efektif sebesar 1,000006. Abstrak bahasa inggris The research of desain of Supercritical Cooled Water Reactor (SCWR) uranium-thorium fuel silinder model has been done. The objective of this research is to obtain the design with high thermal power and inherent safety features. The analyzed parameters were: core fuel enrichment, reactor size, criticality, and power density distribution. A core calculation of column x and row y was achieved by CITATION code. Fuel composition and core configurations in critical condition were calculated by variation of fuel enrichment, reactor size and configuration of the fuel in the core. SCWR used uranium-thorium as fuel, stainless steel as cladding, light water as moderator and coolant as well. This research obtained critical core design that is size x = 340 cm, and y = 170 cm. The critical condition can be achieved when the fuel first region loaded about 3.1704% fuel enrichment, fuel second region 2.5% fuel encrichmant and fuel third region 4% fuel encrichmant. The design produced 1000 M W thermal power, the maximum power density is 114,4073 watts/cm3 and k-effective value is 1.000006. The reactor core in this research fulfills the inherent safety standard in term of neutronic aspect.
| Jenis Karya Akhir: | Skripsi |
|---|---|
| Subyek: | > QC Physics > Teknik Elektro. Rekayasa elektronik Nuklir > Teknik Elektro. Rekayasa elektronik Nuklir |
| Program Studi: | FAKULTAS MIPA > Prodi Fisika |
| Pengguna Deposit: | 0673214 . Digilib |
| Date Deposited: | 29 Sep 2015 03:58 |
| Terakhir diubah: | 29 Sep 2015 03:58 |
| URI: | http://digilib.unila.ac.id/id/eprint/12943 |
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