Preliminary assessment of the BREST reactor design and fuel cycle concept.

Khalil, H. ; Lineberry, J. E. ; Cahalan, J. E. ; Willit, J. L. ; Spencer, B. W.

Technical Information Center Oak Ridge Tennessee

关键词: Research reactors;    Fuel cycles;    Design;    Fast-spectrum reactors;    BREST reactors;   

RP-ID  :  DE2001768560

学科分类：工程和技术（综合）

美国|英语

来源: National Technical Reports Library

【 摘 要 】

A preliminary assessment has been performed of the BREST reactor design and fuel cycle concept being developed by Russian Federation nuclear-power design organizations and research institutes. BREST is an advanced nuclear power concept employing a fast-spectrum reactor, liquid lead coolant, uranium-plutonium nitride fuel, and a pool type plant configuration featuring design simplification and passive 'deterministic' safety as targeted means of achieving cost reduction. A closed fuel cycle that avoids separation of fissile materials, retains a fraction of the fission products in recycled fuel, and minimizes discharge of long-lived radio-toxic nuclides is proposed for eventual large-scale deployment.