ANALISIS PENGARUH DAYA UNTUK PENGUJIAN PIN BAHAN BAKAR TIPE PWR DI PRTF RSG-GAS

Sari

ABSTRAK

ANALISIS PENGARUH DAYA UNTUK PENGUJIAN PIN BAHAN BAKAR TIPE PWR  DI PRTF RSG-GAS.Analisis pengaruh daya untuk pengujian pin bahan bakar tipe Pressurized Water Reactor (PWR) di Power Ramp Test Facility (PRTF) RSG-GAS telah dilakukan dan dianalisis untuk mengetahui pengaruh daya terhadap unjuk kerja pin bahan bakar selama diiradiasi. Fenomena pengaruh daya yang dibangkitkan dari fasilita spengujian PRTF PRSG-GAS sangat signifikan terhadap unjuk kerja bahan bakar. Untuk iniperlu disiapkan program jaminan mutu, fasilitas fabrikasi pin bahan bakar dan analisis unjuk kerja bahan bakar selama pengujian di PRTF RSG-GAS.Program jaminan mutu selama fabrikasi pin bahan bakar dan pengujian hasil selama pra iradiasiantara lain spesifikasi pin bahan bakar tipe PWR, gambar kerja, prosedur, instruksi kerja, lembar kendali. Persiapan fasilitas pengujian PRTF telah dilakukan uji fungsi sistem operasi dan sistem kendali.Prediksi dan analisis unjuk kerja pin bahan bakar selama iradiasi dilakukan dengan menggunakan program kode komputer FEMAXI-V. Kode ini mampu memprediksi pengaruh daya terhadap unjuk kerja termal dan mekanik secara kulitatif, cukup detail selama kondisi tunak dan transien.Telah dilakukan fabrikasi pembuatan pin dummy sebagai bahan uji kemampuan fabrikasi di Instalasi Elemen Bakar Eksperimental (IEBE) dan telah diuji di PRTF dengan tekanan operasi 160 bar dengan hasil baik tidak bocor. Persiapan pembuatan pelet telah berhasil dibuat pelet bahan bakar UO₂ sesuai dengan spesifikasi yang telah ditetapkan sebagai bahan isian pin elemen bakar tipe PWR. Telah dilakukan analisis dengan simulasi posisi pin pada jarak 0; 40; 60; 100; 200; 300; 440 mm terhadap teras untuk menentukan daya (Linear Heat Rate/LHR) yang dibangkitkan menunjukkan bahwa makin tinggi daya yang diberikan atau makin dekat posisi pin terhadap teras reaktor makin besar burn-up yang dihasilkan.

Kata Kunci:elemen bakar nuklir, pin, PWR.

ABSTRACT

POWER EFFECT ANALYSIS FOR THE IRRADIATION TEST OF PWR FUEL PIN IN THE POWER RAMP TEST FACILITY OF RSG-GAS REACTOR. An analysis on theeffect of power for the preparation of irradiation test of PWR fuel pin in the power ramp test facility (PRTF) of RSG-GAS Reactor had been conducted.  The power generated in the reactor would result in a significant effect on the fuel performance.In the preparation of quality assurance programs and of facilities for the prediction of fuel behavior was necessary.  Among the quality assurance measures performed were the determination of PWR fuel pin specifications and the preparation of technical drawings, procedures, instructions, and control sheets.  Works for the preparation of facilities were also conducted.  To prediction and analyze the fuel behavior during irradiation, a FEMAXI-V code was utilized.  The code was capable of qualitatively predicting the power effect on the thermal and the mechanical performances of the fuel in details at both steady and transient states.  A dummy pin of a PWR fuel had been manufactured in the Experimental Fuel Element Installation (EFEI) of PTBN-BATAN to be irradiated in the PRTF at a pressure of 160 bar.  There was no leak found in the dummy pin.  UO₂ pellets that were in accordance with PWR fuel requirements had also been manufactured in the EFEI.  A simulation to determine the linear heat rate (LHR) had been conducted on a pin at a certain distance from the core.  The distances observed were 0, 40, 60, 100, 200, 300, and 440mm.  It could be seen that the higher the power or the shorter the distance, the burnup would be greater.

Keywords: nuclear fuel elements, pin, PWR