Numerical diffusion and the tracking of solute fields in system codes-Reference-Cited by-同舟云学术

Numerical diffusion and the tracking of solute fields in system codes

Published:1998-02 Issue:3 Volume:179 Page:297-319
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Macian-Juan Rafael,Mahaffy John H.

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference50 articles.

1. Allison, C. et al., (Eds.), 1990. RELAP5/MOD3 Code Manual. US Nuclear Regulatory Commission Report NUREG/CR-5535.

2. Alvarez, D. et al., 1995. Boron mixing transient in a PWR vessel. Physical Studies. CSNI-OCDE Specialists Meet. on Boron Dilution Transients, State College, PA, October 1995.

3. Bandini, B.R., 1990. A three-dimensional transient neutronics routine for the TRAC-PF1 reactor thermal-hydraulic computer code. PhD Thesis, Pennsylvania State University.

4. Barre, F., Parent, M., Brun, B., 1992. Advanced numerical methods for thermalhydraulics. CSNI Specialist Meet. on Transient Two-Phase Flow, Aix-en-Provence, France.

5. An implicit finite-difference algorithm for hyperbolic systems in conservation law form;Beam;J. Comput. Phys.,1976

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