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H. Finnemann, F. Bennewitz, and M. R. Wagner, “Interface current techniques for multidimensional reactor calculations,” Atomkernenergie, Vol. 30, No. 2, 1977, pp. 123-128.

has been cited by the following article:

• TITLE: Reconstruction of the Neutron Flux in a Slab Reactor

  AUTHORS: Adilson Costa da Silva, Aquilino Senra Martinez, Alessandro da Cruz Gonçalves

  KEYWORDS: Neutron Diffusion Equation; Neutron Flux; Slab Reactor

  JOURNAL NAME: World Journal of Nuclear Science and Technology, Vol.2 No.4, October 31, 2012

  ABSTRACT: In this electronic article we use the one-dimensional multigroup neutron diffusion equation to reconstruct the neutron flux in a slab reactor from the nuclear parameters of the reactor, boundary and symmetry condition, initial flux andkeff. The diffusion equation was solved analytically for one single homogeneous fuel region and for two regions considering fuel and reflector. To validate the method proposed, the results obtained in this article were compared using reference methods found in the literature.