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:345-356
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Macian-Juan Rafael,Ivanov Kostadin,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

Reference17 articles.

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2. Bandini, B.R., 1990. A Three-Dimensional Transient Neutronics Routine for the TRAC-PF1 Reactor Thermal-Hydraulic Computer Code. PhD thesis, Pennsylvania State University.

3. Diamond, D.J., 1990. Reactivity Accidents. A Reassessment of the Design Basis Events. Brookhaven National Laboratory, NUREG/CR-5368.

4. Edenius, M., Forssen, B., 1989. CASMO-3. A Fuel Assembly Burnup Program, User's Manual. STUDSVIK/NFA-89/3.

5. Interface current technique for multidimensional reactor calculations;Finnemann;Atomkernenergie,1977

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