Lineer-Kuadratik Anizotropik Saçılma için Kritiklik Probleminde Yansıtıcı Özdeğerleri

Tek-hızlı nötron transport teoride son zamanlarda çalışılan lineer-kuadratik anizotropik saçılma fonksiyonu belirli kritik levha kalınlıkları için yansıtıcı öz değerlerini çözmek amacıyla kullanılır. Lineer-kuadratik anizotropik saçılma özelliği gösteren nükleer materyale sahip bir düzlem reaktör göz önüne alınmıştır ve problem yansıtıcı sınır koşullarını içermektedir. Amaç belirli ikincil nötron sayılarına ve belirli reaktör kalınlıklarına göre yansıtıcı katsayılarını bulmaktır. Sayısal sonuçlar Modified FN yöntemi kullanılarak bulunmuştur. 

The Reflection Eigenvalues in the Criticality problem for Linear-Quadratic Anisotropic Scattering

The recently studied Linear-Quadratic anisotropic scattering function in one-speed neutron transport theory is used to solve the reflection eigenvalues for the certain critical slab thicknesses. A slab reactor including the nuclear material is taken into account for the linear-quadratic anisotropic scattering with the reflection boundary condition. The aim is to find the reflection coefficients according to the secondary neutron numbers and the reactor thickness. The numerical results are obtained by using the Modified FN method.

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Süleyman Demirel Üniversitesi Fen Edebiyat Fakültesi Fen Dergisi-Cover
  • Yayın Aralığı: Yılda 3 Sayı
  • Başlangıç: 2006
  • Yayıncı: Süleyman Demirel Üniversitesi Fen-Edebiyat Fakültesi
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