Search - Number 15 - THE CHOICE OF NUCLIDES FOR BURNUP ACCOUNTING AT THE SPENT FUEL RBPB-1000

THE CHOICE OF NUCLIDES FOR BURNUP ACCOUNTING AT THE SPENT FUEL RBPB-1000
Cover not present THE CHOICE OF NUCLIDES FOR BURNUP ACCOUNTING  AT THE SPENT FUEL RBPB-1000
Category: Number 15
Publication: 15
Summary

Composition of sources of neutrons (both at the spontaneous division and due to (a,n)- reaction on oxygen of oxide fuel) of the spent fuel assemblies, speeds of emission of neutrons of every nuclide is ana-lysed . The choice of nuclides for burnup accounting at the spent fuel assemblies is grounded.
Keywords: spent fuel, burnup accounting, emission of neutrons