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Design Study of Very Small Nuclear Power Reactors Based on Liquid

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Design Study of Very Small Nuclear Power Reactors Based on Liquid Prosidillg Seminar Nasional ke-9 Telmologi JaIl Keselamatan PLTN Serta Fasilitas Nllklir Jakarta, 20 AglIstlls 2003 ISSN.. 0854- 2910 STUDI DISAIN REAKTOR DAYA BERUKURAN SANGAT KECIL DENGAN PENDINGIN Pb-Bi DAN BAHAN BAKAR NITRIDA ~r} Zaki Su'ud Jurusan Fisika ITB, JI. Ganesha 10, Bandul1g Telp. 022-2500834, Fax. 022-2506452, cmail:[email protected] ABSTRAK STUDI DISAIN REAKTOR DAYA BERUKURAN SANGAT KECIL DENGAN PENDINGIN Pb-Bi DAN BAHAN BAKAR NITRIDA. Dalam studi ini dikaji tentang karakteristik dan prospek reaktor daya berukuran sangat kecil (10- 20M\Ve) berbasis raJa pendinginPb-Bi cair daBbahan bakar nitrida, Disain reaktor ini menggunakan internal blanket guna meminimisasi ekses reaktivitas selama operasi reaktor. Teras dibagi menjadi beberapa daerah untuk optimasi ekses reaktivitas, power peaking, clankoefisien densitas bahan pendingin. Digunakan teras bebentuk simetri agar penggunaan netronnya efisien. Dengan Fuel volume fraction yang diperbesar permasalahan rendahnya power density yang biasanya monGol raJa reaktor daya berukuran kecil dapat diatasi. Reaktor ini dicanangkan untuk mengatasi krisis listrik di daerah-daerah loafjawa yangjaringan listriknyabelum tertata rapi clanbanda!. ABSTRACT DESIGN STUDYOF VERY SMALL NUCLEAR POWER REACTORS BASED ON LIQUID Pb-Bi COOLANT AND NITRIDE FUEL. In this study the characteristic and prospect of very small size (10-20 MWe) nuclear power reactors based on liquid Pb-Bi coolant and nitride fuel are investigated Theproposed design uses internal blanket to minimize excess reactivity during reactor operation. The reactor core is divided into several region and adjusted to optimized reactivity swing, power peaking and coolant density coefficient of reactivity. As usualfor liquid Pb and Pb-Bi core, the design is also adjusted to minimize pressure drop and maximize natural circulation component. In the present study we used balanced core to optimize nelltronicperformance. U\'ing higher .filel volume fraction we can overcome solution of low power density problem usually appearfor velY small nuclear power reactors. ./ 365 Prosiding Seminal' Nasional ke-9 Telmologi da/l Keselamata/l PLTN Serra Fasilitas Nuklir Jakarta, 20 Agllstus 2003 ISSN.. 0854 - 2910 I. PENDAHULUAN Pada saat ini cadangan energi listrik nasional cukup kritis khususnya untuk berbagai daerah di loaf jawa. Mengingat bahwa kebutuhan tiap provinsi di loaf Jawa tak terlalu besar (umumnya < 100Mwe) sedangkan jaringan distribusi global belum ada maka reaktor moduler berukuran kecil akan menjadi solusi yang tepat. Sebagai . gambaran tabel berikut menunjukkansituasi cadangan energi listrik kita. Tabel 1: Bebera,ea daerah kritis listrik ... ........ ""............. <N9L ::.A.tenlJ?t&vjhce: .. ... 'Qhp~~hM:: J?¥aR)j(j~a i.:D~n~.t':::.::: 1. Aceh 31 46 -15 2. West Sumatra and Riau 210 234 -24 3. South part of Sumatra 654 665 -11 4. Bangka Belitung Island 19 23 -4 5. West Kalimantan 30 36 -6 6. East Kalimantan 150 165 -15 7. South & Central Kalimantan 161 204 -43 Source: Indonesian Electricity Company (PLN) web site, June 10, 2003 Tabel 2 : Pcl"tllmblihan konsllmsi listrik Indonesia i-Peak Demand (GW) i 13.326! 14.174; 14.862115.844;116.9651 18,168! .~~--;-Energy Sales (TWit) ; 16.41 i 17.63 ! 19.39 'I 21.41 :1 23.721 26.28; i-Peak Demand (GW) ; 3.85 ; 4.12 ; 4.52 :i 4.98 :: 5.501 6.07,; 1111m1~I~lli~lllr§'i.~p~li~I~I~ii~l~liii~iiii~~{~IJ~1~]11~1~~~~111i~U;~]~JI]~I;;~1~~~11il;;,] Source: Indonesian Electric Company (PLN) web site, June 10, 2003 Penelitian ini bertujuan untuk mendesain berbagai reactor nllklir masa depan yang sesllai dengan lingkungan alam clan kebutuhan masyarakat Indonesia, dengan fokus utama reaktor kecil yang dapat berumur sang at lama tanpa perlu refueling. 366 Prosidi/lg Seminar Nasional ke-9 Teknologi dan Keselamatan PLTN Serra Fasilitas Nuklir Jakarta, 20 AglIstlls 2003 ISSN: 0854 -2910 Dalam studi ini dirancang reaktor daya sangat kecil tetapi karena kompak dapat cukup kompetitif clan mampu mencapai burnup standar diatas 8%HM untuk 15-25 tahun operasi tanpa refueling ll. KONSEP DISAIN Reaktor daya kecil biasanyamemiliki ekonomi netron yang rendah clan karenanya dalam disain ini digunakan fuel volume fraction yang lebih besar clan reflektor yang sedikit lebih tebal untuk meningkatkan ekonomi netron. Di Slm digunakan plutonium dari PWR sebagaiplutonium awal dalam operasinya. Sebagaimana yang selama ini digunakan, blanket internal di tengah teras reaktor untuk meningkatkan rasio konversi dalam (internal convertion ratio) sehingga ekses reaktivitas dapat ditekan dalamwaktu operasi yang relatif lama. Pendingin Pb-Bi memiliki banyak keunggulan antara lain spektrum yang keras menyebabkan hilangnya absorbsi akibat pergeseran spektrum menyusul hilanglberkurangnya bahan pendingin dapat dikurangi. Pb-Bi juga digunakan sebagai reflektor. Untuk mencegah probl~m korosi yang akut maka digunakan temperatur operasi yang sedikit lebihrendah : 325 -450°c. Untuk meningkatkan kemampuan inherent safety maka diusahakan untuk dapat dioperasikan secara sirkulasi alamiah atau sekurangnya daya sirkulasi alamiahnya mencapai 75%. Selanjutnya akan dilakukan perhitungan untuk beberapa level daya pacta tingkat rendah untuk mengoptimasi penggunaan di daerah-daerah loaf jawa yang relatif bervariasi. III. METODA PERHITUNGAN lnformasi detil tentang langkah perhitungan ini dapat dilihat pacta pustaka nomor 3. Untuk perhitungan netronik digunakan program komputer 2 clan 3 dimensi untuk analisa difusi multigrup clan burnup. Persamaan difusi multigrup untuk kasus 2 clan 3 dimensi dipecahkan dengan skema hecla hingga clan dengan menerapkan iterasi luar- iterasi dalam. Iterasi dalam digunakan metoda SOR, sedang iterasi loaf digunakan modified power method sehingga memungkinkan memasukkan faktor akselerasi pacta iterasi loaf. Perhitungan dilakukan dalam 8 grup energi netron. Penampang lintang reaksi didapatkan dari kode komputer SLAROM clan FIITB-CHl. Untuk perhitungan burnup maka digunakan metoda semi analitik sebagaimana dijelaskan dalam referensi. 367 - --~ ~--- Prosidillg Semillar Nasiollo/ ke-9 Tekll%gi doll Kese/amatall PLTN Serlo Fasilitas Nllk/ir Jakarta, 20 AglIstlls 2003 ISSN: 085./ - 29] 0 IV. HASIL PERHITUNGAN Untuk contoh perhitungan yang dibahas di sini digunakan parameter-parameter sistem sebagaimana yang ditunjukkan dalam tabel berikut. Tabel 3: Sample design parameters .... ........ ..... .......... :t>.A1t&MJtXlE(R.? .SttElnIC*TIQN........ .'. Reactor Power 50 MWth (- 20 Mwe) Average Burnup 10% HM Peak burnup 12% HM Coolant Pb-Bi Shielding Material B4C + Stainless steel Fuel Material UN-PuN Fuel Enrichment 9.5 - 12.5% Inlet Temperature 3250 C Average outlet temperature 4500 C Core volume fraction Fuel 40-50%(inner blanket),50-60%(main core) Structure 10-20% Coolant 30-35% Core Size R Z Inner Core width 14.7 cm 14.7 cm Outer core width 10 cm . 10 cm Inner blanket width 15 cm 15 cm Reflector & Shielding 50 cm 50 cm Reactor Life time 20 years continuesly (without refueling & reshufflin,g) Reactivity swing < O.4%dk/k (slightly below 1$) lhR P/'OsidillgSemillar Nasiollal ke-9 Teknologi dan Keselamalall PLTN Serla FilSililas Nllklir Jakarla, 20 AglIsllis 2003 ISSN: OS54 - 2910 Gambar 1: Distribusi daya axial pada awal operasi (BOL) Gambar 2: Distribusi daya axial setelah 15 tahun operasi 369 ~= -- Prosie/illK Sell/illar Nasiollal ke-9 Tekllologi e/all Keselall/alall PLTN Serla Fasililas Nllklir Jakarla. 20 AgIIslus 2003 ISSN: 085.1 - 2910 Gambar 3: Distribusi daya aksial pad a 30 tahun operasi (EOL) Gambar 4 : Perubahan reaktivitas sebagai fungsi waktu Tampak bahwa dengan ekses reaktivitas yang msih di bawah I dollar. Dengan konsep yang digunakan di sini kontribusi bagian tengah teras pada daya reaktor secara keseluruhan menjadi penting pada pertengahan clanakhir usia operasi. Dengan kerapatan daya puncak mencapailebih dari 100 W/cc maka efisiensi pengoperasian reaktor akan cukup baik bagi ukuran reaktor daya sangat keeil. lni perlu 370 Prosiding Seminar Nasional ke-9 Teknologi clanKeselamatan PLTN Serra Fasilitas Nuklir Jakarta, 20 Agustlls 2003 ISSN.. 0854 - 2910 dioptimasikan lebioh lanjut pada analisa lebih rinci pada termohidrolika untuk mendapatkan porsi sirkulasi alamiahyang besar meneapaisekitar 50% atau lebih. Dari label I juga tampak bahwa peneapaian burnup eukup besar clan relatif sebanding dengan LMFBR standar sehingga dapat digunakan komponen yang standar digunakan dalam LMFBR besar berpendinginPb-Bi. Terakhir masalah korosi perlu mendapat perhatian khusus terutama untuk operasi dalam rentang waktu sangat lama. V. KESIMPULAN Telah diperoleh disain reaktor daya sangat keeil namun kompak sehingga diharapkan bersifat kompetitif. Reaktor ini menggunakan porsi fraksi volum bahan bakar yang eukup besar. Dalam 30 tahun operasi mampu meneapai level burnup yang sebanding dengan reaktor besar. DAFTAR PUSTAKA 1. Zaki Sand H. Sekimoto, Annal ofNucIear energy, 22,(1995) p. 711 2. Zaki S , Progress ofnucIear Energy, Vol. 32, No. 3/4 pp. 571. 3. Zaki Sand H. Sekimoto, Nue\. Eng. And Design, Vol 162, 1996 371.
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