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THERMAL-HYDRAULIC PERFORMANCE OF HIGH POWER RESEARCH REACTOR CORE DESIGN AS A FUNCTION OF URANIUM FUEL DENSITY

Endiah Puji Hastuti, EPH and Lily Suparlina, LS and Supardjo, Supardjo (2016) THERMAL-HYDRAULIC PERFORMANCE OF HIGH POWER RESEARCH REACTOR CORE DESIGN AS A FUNCTION OF URANIUM FUEL DENSITY. In: Prosiding Seminar Nasional Teknologi Energi Nuklir 2016, 4-5 Agustus 2016, BATAM.

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Abstract

ABSTRACT THERMAL-HYDRAULIC PERFORMANCE OF HIGH POWER RESEARCH REACTOR CORE DESIGN AS A FUNCTION OF URANIUM FUEL DENSITY. BATAN has a program to design high power research reactor. This design is aimed to anticipate Indonesia’s plan to construct new research reactor as a replacement of the existing research reactors that are closing to their operation lifetime. At the same time, this program is used to increased BATAN’s human resource development in reactor technology. This research reactor is designed to follow the future trend that has high power and can generate average neutron flux as high as 1.0×1015 n/cm2 s and thermal neutron flux of 5.0×1015 n/cm2 s with reactor power of 50 MW. The regulation on the limitation of research reactor fuel enrichment less than 20% triggered the research and development on fuel loading that can achieve neutron flux as high as possible. This research is meant to analyze the results of neutronic calculation on the effect of U-9Mo fuel loading in fresh and equilibrium condition to the core thermohydraulic performance of high power research reactor. The calculation was carried out using diffusion code Batan-3diff and modified PARET-ANL. The analysis on the effect of fuel loading to the distribution of power peaking factor of the high power research reactor core in fresh and equilibrium condition indicates the significant effect on fuel and coolant thermal characteristics. The analysis results show that U-9Mo fuel with U235 isotope loading of 360, 390, and 450 g, either in fresh and equilibrium condition with all control rods withdrawn, fulfills the requirements for high power research reactor fuel. The use of U-9Mo with 450 g is much more preferred as it has the longer in-core residence time than the other fuel loading levels. Keyword: research reactor, high power, uranium density, thermal hydraulic performance. ABSTRAK PERFORMA TERMOHIDROLIKA PADA DESAIN TERAS REAKTOR RISET DAYA TINGGI SEBAGAI FUNGSI DENSITAS URANIUM BAHAN BAKAR. BATAN mempunyai program untuk mendesain reaktor riset daya tinggi. Desain tersebut bertujuan untuk mengantisipasi apabila Indonesia akan membangun reaktor riset baru sebagai pengganti reaktor riset yang akan berakhir umur operasinya. Program tersebut sekaligus penting untuk meningkatkan kemampuan SDM BATAN di bidang Teknologi Reaktor. Reaktor riset ini didesain mengikuti trend masa depan yaitu memiliki daya tinggi dan dapat menghasilkan fluks neutron rerata sebesar 1.0×1015 n/cm2 s dan fluks neutron termal sebesar 5.0×1014 n/cm2 s, dengan daya reaktor 50 MW. Adanya peraturan penggunaan bahan bakar reaktor riset dengan pengayaan uranium kurang dari 20% memicu pengembangan penelitian terhadap tingkat muat bahan bakar yang memungkinkan untuk dapat menghasilkan fluks neutron setinggi mungkin. Tujuan penelitian untuk mengetahui pengaruh densitas uranium bahan bakar U-9Mo pada kondisi segar (fresh) dan setimbang (equilibrium) terhadap performa termohidrolika teras reaktor riset dengan daya tinggi. Perhitungan dilakukan menggunakan program perhitungan neutronik difusi Batan-3diff dan PARET-ANL yang termodifikasi. Analisis pengaruh densitas uranium bahan bakar pada distribusi faktor puncak daya teras reaktor riset daya tinggi pada kondisi bahan bakar fresh fuel dan equilibrium. Hasil studi menunjukkan bahwa bahan bakar U-9Mo dengan densitas uranium 360, 390 dan 450 g, baik pada kondisi fresh maupun equilibrium dengan posisi batang kendali ditarik seluruhnya, memenuhi syarat menjadi bahan bakar reaktor riset daya tinggi. Namun demikian penggunaan bahan bakar dengan densitas uranium 450 g lebih menguntungkan karena mempunyai waktu tinggal di dalam reaktor lebih lama dibandingkan uranium dengan densitas lainnya. Kata kunci: reaktor riset, daya tinggi, densitas uranium, kinerja termohidrolika

Item Type: Conference or Workshop Item (Paper)
Subjects: Keselamatan dan Keamanan Nuklir
Divisions: Pusat Teknologi dan Keselamatan Reaktor Nuklir
Depositing User: USER PTKRN BATAN
Date Deposited: 21 May 2018 07:38
Last Modified: 21 May 2018 07:38
URI: http://repo-nkm.batan.go.id/id/eprint/2185

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