Hızlı nötron reaktörlerinde yakıt malzemesi olarak kullanılan 235,238U ve 239Pu izotoplarına yönelik tesir kesiti hesaplamaları için nükleer seviye yoğunluğu parametresinin incelenmesi
Öz
Bu çalışmada, hızlı nötron reaktörlerinde
yakıt malzemesi olarak kullanılan 235U, 238U ve 239Pu izotoplarının 1-30MeV enerjili hızlı nötronlar ile
(n,f) reaksiyon tesir kesitleri teorik olarak seviye yoğunluğu modelleri
kullanarak incelenmiştir. Seviye yoğunluğu ve seviye yoğunluğu parametreleri,
çekirdeğin yapısal özelliklerini tanımlamada ve reaksiyon tesir kesiti
hesaplamalarında çok önemli bir veridir. Reaktör tasarımlarında kullanılacak
malzemeler için tasarım öncesi teorik olarak hesaplanan nükleer fisyon tesir
kesiti verileri kullanılır. Bahsedilen açıklamalar göz önüne alınarak; bu
çalışmada, TALYS 1.8 bilgisayar kodu kullanılarak teorik nükleer reaksiyon
tesir kesiti hesaplamaları farklı seviye yoğunluğu modelleri ile
gerçekleştirilmiştir. Seviye yoğunluğu parametrelerinden “a” değiştirerek,
enerjiye bağlı olarak teorik tesir kesit sonuçlarını deneysel tesir kesiti
sonuçları ile uyumlu olacak bir parametre analizi yapılmıştır ve (n,f)
reaksiyonu için teorik olarak kullanılabilecek bir seviye yoğunluğu modeli
önerisi ile parametresi elde edilmiştir.
Anahtar Kelimeler
Hızlı nötron reaktörü yakıt malzemesi tesir kesiti seviye yoğunluğu parametresi TALYS
Kaynakça
- World Nuclear Association, http://www.world-nuclear.org, (01.06.2017).
- Hızlı Üretken Reaktörler, http://www.nukleer.web.tr/nukleer_santral_turleri/fbr_ana.html, (01.06.2017).
- What is Nuclear? / What is a fast reactor? https://whatisnuclear.com/articles/fast_reactor.html, (01.06.2017).
- Kaplan, A., Sarpün, İ.H., Aydin, A., Tel, E., Çapalı, V. and Özdoğan H., (g,2n) reaction crosssection calculations of several even–even lanthanide nuclei using different level density models, Physics of Atomic Nuclei, 78, 1, 53-64, (2015).
- Demir B., Kaplan A., Çapalı V., Özdoğan H., Sarpün, İ.H., Aydın A. and Tel E., Neutron production cross–section and geant4 calculations of the structural fusion material 59Co for (a,xn) and (g,xn) reactions, Journal of Fusion Energy, 34 (3), 636-641, (2015).
- Kaplan, A., Şekerci, M., Çapalı, V. and Özdoğan, H., Computations of (a,xn) reaction cross-section for107,109Ag coated materials with possible application in accelerators and nuclear systems, Journal of Fusion Energy, 35, 4, 715–723, (2016)
- Sarpün, İ.H., Aydın, A., Kaplan, A., Koca, H. and Tel, E., Comparison of fission barrier and level density models in (a,f) reactions of some heavy nuclei, Annals of Nuclear Energy, 70, 175-179, (2014).
- Koning, A., Hilaire, S. and Goriely, S., TALYS-1.8a nuclear reaction program, user manual (nrg, the Netherlands), first edition: December 26, 2015 (2015).
- Brookhaven National Laboratory, National Nuclear Data Center, EXFOR/CSISRS (Experimental Nuclear Reaction Data File). Database Version of June 16, 2017 (2017), (http://www.nndc.bnl.gov/exfor/)
- RIPL–reference input parameter library for calculation of nuclear reactions and nuclear data evaluations, Nuclear Data Sheets 110, 3107 (2009).
- Ignatyuk, A.V., Smirenkin G.N. and Tishin, A.S., Contrubution of collective motion to density of excited states of a nucleus, Soviet Journal of Nuclear Physics, 21, 3, 255-612, (1975).
- Gilbert, A. and Cameron, A.G.W., A composite nuclear-level density formula with Shell corrections, Canadian Journal of Physics, 43, 1446-1496, (1965).
- Dilg, W., Schantl, W., Vonach, H. and Uhl, M., Level density parameters for the back-shifted Fermi gas model in the mass range 40 < a < 250, Nuclear Physics A, 217, 269-298, (1973).
- Baba, H., A shell-model nuclear level density, Nuclear Physics A, 159, 625-641 (1970).
Investigation of nuclear level density parameter for the cross section calculations of 235,238U and 239Pu isotopes used as fuel materials in fast neutron reactors
Öz
In this study, the reaction cross sections of (n,f)
reactions with 1-30 MeV energetic neutrons on 235U, 238U
and 239Pu isotopes which have been using as fuel materials in fast
neutron reactors were theoretically investigated using level density models.
Level density and level density parameters are very important to describe the
structural properties of the nucleus and to calculate the reaction cross
section. For the materials to be used in the reactor designs, the theoretically
computed nuclear fusion cross section data is used before the design. Taking
into account the aforementioned statements; in this study, the theoretical
nuclear reaction cross section calculations using TALYS 1.8 computer code were
performed with the different level density models. By changing the level
density parameter “a”, a parameter analysis based on the energy was performed
using statistical methods in where the theoretical cross section results would
be consistent with the experimental cross section results and its parameter
that can be used theoretically for the (n, f) reaction with 1-10 MeV energetic
neutrons are obtained.
Anahtar Kelimeler
Fast neutron reactor fuel material cross section level density parameter TALYS
Kaynakça
- World Nuclear Association, http://www.world-nuclear.org, (01.06.2017).
- Hızlı Üretken Reaktörler, http://www.nukleer.web.tr/nukleer_santral_turleri/fbr_ana.html, (01.06.2017).
- What is Nuclear? / What is a fast reactor? https://whatisnuclear.com/articles/fast_reactor.html, (01.06.2017).
- Kaplan, A., Sarpün, İ.H., Aydin, A., Tel, E., Çapalı, V. and Özdoğan H., (g,2n) reaction crosssection calculations of several even–even lanthanide nuclei using different level density models, Physics of Atomic Nuclei, 78, 1, 53-64, (2015).
- Demir B., Kaplan A., Çapalı V., Özdoğan H., Sarpün, İ.H., Aydın A. and Tel E., Neutron production cross–section and geant4 calculations of the structural fusion material 59Co for (a,xn) and (g,xn) reactions, Journal of Fusion Energy, 34 (3), 636-641, (2015).
- Kaplan, A., Şekerci, M., Çapalı, V. and Özdoğan, H., Computations of (a,xn) reaction cross-section for107,109Ag coated materials with possible application in accelerators and nuclear systems, Journal of Fusion Energy, 35, 4, 715–723, (2016)
- Sarpün, İ.H., Aydın, A., Kaplan, A., Koca, H. and Tel, E., Comparison of fission barrier and level density models in (a,f) reactions of some heavy nuclei, Annals of Nuclear Energy, 70, 175-179, (2014).
- Koning, A., Hilaire, S. and Goriely, S., TALYS-1.8a nuclear reaction program, user manual (nrg, the Netherlands), first edition: December 26, 2015 (2015).
- Brookhaven National Laboratory, National Nuclear Data Center, EXFOR/CSISRS (Experimental Nuclear Reaction Data File). Database Version of June 16, 2017 (2017), (http://www.nndc.bnl.gov/exfor/)
- RIPL–reference input parameter library for calculation of nuclear reactions and nuclear data evaluations, Nuclear Data Sheets 110, 3107 (2009).
- Ignatyuk, A.V., Smirenkin G.N. and Tishin, A.S., Contrubution of collective motion to density of excited states of a nucleus, Soviet Journal of Nuclear Physics, 21, 3, 255-612, (1975).
- Gilbert, A. and Cameron, A.G.W., A composite nuclear-level density formula with Shell corrections, Canadian Journal of Physics, 43, 1446-1496, (1965).
- Dilg, W., Schantl, W., Vonach, H. and Uhl, M., Level density parameters for the back-shifted Fermi gas model in the mass range 40 < a < 250, Nuclear Physics A, 217, 269-298, (1973).
- Baba, H., A shell-model nuclear level density, Nuclear Physics A, 159, 625-641 (1970).
Ayrıntılar
| Bölüm | Araştırma Makalesi |
|---|---|
| Yazarlar | |
| Yayımlanma Tarihi | 7 Aralık 2017 |
| Gönderilme Tarihi | 15 Ağustos 2017 |
| Yayımlandığı Sayı | Yıl 2017 Cilt: 19 Sayı: 3 |