Pengaruh Perubahan Fraksi Volume Terhadap Kekritisan Desain Gas-Cooled Fast Reactor Berbahan Bakar Uranium Nitride

Sari Novalianda (Fakultas Teknik Universitas Al-Azhar)
Andri Ramadhan (Fakultas Teknik Universitas Al-Azhar)

Jurnal Fisika Unand
Vol 9 No 4 (2020)

Penelitian ini menyajikan pengaruh perubahan fraksi volume desain         Gas-Cooled Fast Reactor (GFR) berbahan bakar Uranium Nitride. Fraksi volume reaktor cepat terdiri dari bahan bakar, kelongsong dan pendingin. Penelitian ini terdiri dari tiga desain sel bahan bakar dengan perbedaan fraksi voleme yang terdiri dari fuel, caldding, dan coolant yaitu desain A 55%:10%:35%, desain B 60%:10%:30% dan 65%:10%:25% untuk desain C. Parameter survey yang diukur adalah faktor kekritisan reaktor yaitu keff, kinf dan perubahan level burnup terhadap waktu burnupnya. Perhitungan desain GFR menggunakan seperangkat program Standart Reactor Analysis Code (SRAC). Hasil perhitungan ketiga desain reaktor, didapat bahwa  desain B berbahan bakar Uranium Nitride dengan pengayaan 9,5% uranium 235 dan fraksi volume 60% bahan bakar, 10 % kelongsong dan 30% pendingin mencapai kondisi kritis pada keff > 1,008 dan kinf > 1,012. Desain reaktor B dapat beroperasi selama 10 tahun tanpa proses refueling dengan excess reactivity 0,031%. The research presents the effect of changes in the volume fraction on the criticality of the Uranium Nitride Gas-Cooled Fast Reactor (GFR) design. The fast reactor volume fraction consists of fuel, cladding, and coolant. This research consisted of three fuel cell designs his research consists of three fuel cell designs with different volumes fraction consisting of fuel, cladding, and coolant namely A design 55%:10%:35%. B design 60%:10%:30% and 65%:10%:25% for C design. The survey parameters measured were the criticality of the reactor, namely keff, kinf, and burnup level changes with the burnup time. GFR design calculations use a set of Standard Reactor Analysis Code (SRAC) programs. The third calculation of the reactor design, found that design B was fueled with Uranium Nitride with enrichment of 9.5% uranium 235 and volume fraction of 60% fuel, 10% cladding, and 30% coolant reached critical conditions at keff> 1,008 and kinf> 1,012. Design B reactor can operate for 10 years without refueling with an excess reactivity of 0.031%.