ASYMPTOTIC REACTOR THEORY

Journal Article · Tue Aug 01 04:00:00 EDT 1961 · Nuclear Sci. and Eng.

OSTI ID:4841220

Case, K M; Ferziger, J H; Zweifel, P F

It is shown that the results of -- asymptotic reactor theory may be derived simply from the condition that an infinite medium (rather than the correct finite medium) diffusion equation be used to describe the thermal neutron fiux in a reactor. In an asymptotic (bare, homogeneous, thermal) reactor, it is possible to describe the thermal flux through such an equation if the kernel of the infinite medium equation is defined properly, even when the reactor is not ''large.'' The relation between the kernels of the two equations is explicitly derived, and the conditions examined under which the kernel of the infinite medium equation can be interpreted physically as the Green' function of the infinite medium slowing-down problem. It is found that this interpretation is not restricted to the case in which the infinite medium, slowing-down problem can be treated accurately by diffusion theory. Rather, the restriction is that the '' asymptotic'' portion of the flux give a reasonably accurate description of the finite medium Green's function. Thus, the use of transport kernels in asymptotic reactor theory is meaningful. (auth)

• Research Organization: Univ. of Michigan, Ann Arbor
• NSA Number: NSA-15-028773
• OSTI ID: 4841220
• Journal Information: Nuclear Sci. and Eng., Journal Name: Nuclear Sci. and Eng. Vol. Vol: 10
• Country of Publication: Country unknown/Code not available
• Language: English

Related Subjects

DIFFERENTIAL EQUATIONS
DIFFUSION
GREEN FUNCTION
MATHEMATICS
NEUTRON FLUX
REACTOR TECHNOLOGY
REACTORS
SLOWDOWN
THERMAL NEUTRONS
TRANSPORT THEORY