
Accession Number : AD0621791
Title : RESEARCH ON RADIATION SHIELDING,
Corporate Author : SOCIETA RICERCHE IMPIANTI NUCLEARI SALUGGIA (ITALY) CENTRO RICERCHE NUCLEARI
Personal Author(s) : Canali,U. ; matthes,W. ; Nicks,R. ; Papmehl,N. ; Penkuhn,H.
Report Date : 1964
Pagination or Media Count : 23
Abstract : An analytical method of treating energydependent neutron transport problems is discussed. Solutions are found by expanding the angular neutron flux in eigenfunctions of the energy transfer operator. Integral representation of the solution instead of a series expansion is given. A numerical method for the integration of the Boltzmann transport equation for gammas is described. The results of a monoenergetic collimated beam incident on a slab of Fe and Pb are given. Buildup factors are compared with those given by Goldstein. Experimental work was carried out in fast neutron propagation in water. Monoenergetic neutrons were produced by a 5.5 Mev Van de Graaf accelerator. Water and oxygen removal crosssections as a function of energy are given. Neutron penetration in ducts surrounded by water was investigated. The neutron source was a natural uranium convertor plate. Fast and thermal neutron flux profiles on the axis of the cylindrical ducts were measured with threshold and resonance detectors. Asymptotic slopes of fast neutron profiles are given. (Author)
Descriptors : (*REACTOR SHIELDING MATERIALS, NUCLEAR PARTICLES), NEUTRON TRANSPORT THEORY, GAMMA RAY ABSORPTION COEFFICIENTS, NEUTRON FLUX, FAST NEUTRONS, THERMAL NEUTRONS, TRANSPORT PROPERTIES, PARTIAL DIFFERENTIAL EQUATIONS, WATER, LEAD(METAL), IRON, ITALY
Distribution Statement : APPROVED FOR PUBLIC RELEASE