English (United Kingdom)

https://curated-unify.zendy.io/wp-json/zendy-region/v1/featured_content/oa?rat=en

https://curated-unify.zendy.io/wp-json/zendy-region/v1/highlighted_journal/

Global: Zendy Tools annual

Presents the keyphrase highlighting as premium feature

Keyphrase Highlighting

Presents the summarisation as premium feature

Summarisation

Insights

Presents the pdf analysis as premium feature

PDF Analysis

Presents the zaia usage as premium feature

ZAIA

Global: Zendy Tools monthly

Global: Zendy Plus monthly

Presents the access of premium content as premium feature

Premium Content

Global: Zendy Plus annual

Global: Zendy Free Plan

In this paper a methodology is described to estimate multigroup neutronsource distributions which must be added into a subcritical system to drive itto a steady state prescribed power distribution. This work has been motivatedby the principle of operation of the ADS (Accelerator Driven System) reactors,which have subcritical cores stabilized by the action of external sources. Weuse the energy multigroup two-dimensional neutron transport equation in thediscrete ordinates formulation (SN) and the equation which is adjoint to it,whose solution is interpreted here as a distribution measuring the importanceof the angular flux of neutrons to a linear functional. These equations arecorrelated through a reciprocity relation, leading to a relationship betweenthe interior sources of neutrons and the power produced by unit length ofheight of the domain. A coarse-mesh numerical method of the spectral nodalclass, referred to as adjoint response matrix constant-nodal method, is appliedto numerically solve the adjoint SN equations. Numerical experiments areperformed to analyze the accuracy of the present methodology so as toillustrate its potential practical applications.

On the calculation of neutron sources generating steady prescribed power  distributions in subcritical systems using multigroup X,Y-geometry discrete  ordinates models