UC, $UC_2$ ve $U_2C_3$ yakıtlarının füzyon nötron kaynaklı bir hibrid reaktörde değerlendirilmesi

Bu çalışmada (D.T) fuzyon nötron kaynaklı ve yakıt olarak UC, $UC_2$ ve $U_2C_3$ kullanılan bir hibrid mantonun 48 aylık reaktör çalışma süresince fisil yakıt üretimi açısından nötronik performansı araştırılmıştır. Reaktör yakıt bölgesinde soğutucu olarak ötektoid lityum kullanılmıştır. Çalışmada ilk duvar füzyon nötron akısı 5 MW/m2 ve tesis faktörü % 75 dir. Tüm yakıt modellerinde homojen güç için manto enerji çoğaltım faktörü (M), trityum üretimi (TBR), kümülatif fisil yakıt zenginleştirmesi (CFFE), yanma oranı (BU), yakıt gençleştirme kabiliyeti (FOM) ve ısı ayrılması hesaplamaları yapılmıştır. Hibrid mantoda yakıt tipine bağlı olarak % 3-4 'lük zenginleştirme durumuna, yakıt çubuklarının $UC_2$ ihtiva ettiği durumda 18 ve 30, UC ve $U_2C_3$ yakıtlarda 20 ve 30 aylık çalışma süresinde ulaşıldı. En iyi trityum üretim oranı UC yakıtlı modelde elde edildi, bunu sırayla $U_2C_3$ ve $UC_2$ yakıtlar takip etmektedir.

Evaluation of UC,$UC_2$ ve$U_2C_3$ fuels in a hybrid reactor with fusion neutron source

In this study from the point of fissile fuel breeding neutronic performance is investigated in a hybrid manto with fusion neutron source using UC,$UC_2$ and $U_2C_3$ as fuels during 48 mounth reactor operation time. Eutectic lithium was used as coolant in the reactors fuel zone. A first-wall fusion neutron current load 5 MW/m2 and plant factor 75 % . For all fuel models neutronic calculations were done for cumulative fissile fuel enrichment (CFFE), energy multiplication factor (M), tritium breeding ratio (TBR), fuel burn-up , fuel regeneration ability (FOM) and heat release. At the end of operation time, according fuel the enrichments of the 3-4 % were achieved for operation time of 18 and 30 mouth in case of fuel rods containing $UC_2$, respectively and for operation time of the 20 and 30 mouth in case of fuel rods containing UC and $U_2C_3$. The best tritium breeding ratio is obtained in UC, and followed by $U_2C_3$ and $UC_2$.

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1. Hafele,W. “Technical safety Measures and Rules in the Nuclear Field” .Atomwirtschaf, Atomtechnik, October 1989

2. Şahin, S., Yapıcı, H., “Rejuvenation of CANDU Spent Fuel in a Hybrid Manto”, Trans. Am. Nucl. Soc. 59 (1989) 105.

3. Şahin, S., Yapıcı, H., “Investigation of the Neutronic Potential of Moderated and Fast (D, T) Hybrid Blankets for Rejuvenation of CANDU Spent Fuel”. Fusion Technology 16 (1989) . 331.

4. Şahin, S., Yapıcı, H., Baltacıoğlu, E., “Heavy Water Reactor Spent Fuel Regeneration with Fusion Neutrons”. Trans. Am. Nucl. Soc. 60 (1989) 176.

5. Şahin, S., Baltacıoğlu, E., Yapıcı, H., “Potential of a Catalyzed Fusion Driven Hybrid Reactor for the Regeneration of CANDU Spent Fuel”. Fusion Technology 20 (1991) 26.

6. Şahin, S., Yapıcı, H., Baltacıoğlu, E., “Regeneration of LWR Spent Fuel in Hybrid Reactors”. Kerntechnik. 59, No. 6, (Nov. 1994) 270.

7. Teller, E., Fusion, Magnetic Confinement. vol .1, part B, Academic Press (1981).

8. Engle, W.W., Jr, ANISN, “A One-Dimensional Discrete Ordinates Transport Code with Anisotropic Scattering”, K1693, OAK Ridge National Laboatory, 1970

9. Al-Kusayer, T.A., Şahin, S., Drira, A., “CLAW-IV Coupled 30 Neutrons 12 Gamma- Ray Group Section with Retrival Programs for Radiation Transport Calculations”, Radiation Shielding Information Center, OAK Ridge National Laboatory, RSIC-Newletter, pp.4, May.1988

10. Şahin, S., Yapıcı, H., Baltacıoğlu, E., “Fusion Breeder with Enchanced Safeguarding Capabilities Aganist Nuclear Weapon Proliferation”, Energy Convers.Mgmt Vol.00.No.0.pp.1-11, 1998

11. Şahin, S., Al-Kusayer, T.A., Raooff, M.A., “Preliminary Design Studies of a Cylindrical Experimental Hybrid Blanket with Deuterium-Tritium Driver”. Fusion Technology, 10, 84(1986)

12. S.Şahin, Physics of FusionFission (Hybrid) Reactors. 8th International Summer College on Physics and Contemporary Needs, Islamabad, Pakistan, 23, 124 July11 August 1983.

13. S.Şahin, Mainline FusionFission (hybrid) Reactor Concepts, Ecole Polytechnique Federale de Lausanne Institut de Genie Atomique PHBEcublens, Switzerland.