Investigation of the flattened fissile fuel enrichment possibility with a (D, T) driven hybrid blanket cooled by flibe (Li2BeF4)

Author:

Akansu S.Orhan,Ünalan Sebahattin

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference24 articles.

1. Al-Kusayer, T.A., Şahin, S., Drira, A., 1988. CLAW-IV, Coupled 30 Neutrons, 12 Gamma-ray Group Cross-sections with Retrieval Programs for Radiation Transport Calculations. RSIC newsletter. Radiation Shielding Information Center, Oak Ridge, TN.

2. Barett, R.J., MacFarlane, R.E.,1979. CLAW, Coupled 30 Neutrons, 12 Gamma-ray Group Cross-sections for Neutron Transport Calculations. LA-7808-MS, Los Alamos Scientific Laboratory, Los Alamos, NM.

3. Group Constants for Nuclear Reactor Calculations,1964

4. Hybrids for direct enrichment and self-protected fissile fuel production;Conn;Nuclear Technology,1980

5. Engle Jr., W.W., 1970. ANISN, a One-dimensional Discrete Ordinates Transport Code with Anisotropic Scattering. K1693, Oak Ridge National Laboratory, Oak Ridge, TN.

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