Progress in nodal methods for the solution of the neutron diffusion and transport equations

Author:

Lawrence R.D.

Publisher

Elsevier BV

Subject

Waste Management and Disposal,Energy Engineering and Power Technology,Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering

Reference111 articles.

1. PDQ—An Ibm-704 Code to solve the two-dimensional few-group neutron diffusion equations;Bilodeau,1957

2. Nuclear Reactor Analysis;Henry,1975

3. FLARE, A three-dimensional boiling water reactor simulator;Delp,1964

4. Nodal methods for three-dimensional simulators;Gupta;Prog. Nucl. Energy,1981

5. Refinements in accuracy of coarsemesh finite-difference solution of the group-diffusion equations;Henry,1972

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