Evaluation of the use of nodal methods for MTR neutronic analysis [electronic resource].

Published:: Argonne, Ill. : Argonne National Laboratory, 1997.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description:: pages 274-284 : digital, PDF file
Additional Creators:: Argonne National Laboratory and United States. Department of Energy. Office of Scientific and Technical Information

Access Online

www.osti.gov

Availability

Finding items...

Restrictions on Access:

Free-to-read Unrestricted online access

Summary:

Although modern nodal methods are used extensively in the nuclear power industry, their use for research reactor analysis has been very limited. The suitability of nodal methods for material testing reactor analysis is investigated with the emphasis on the modelling of the core region (fuel assemblies). The nodal approach`s performance is compared with that of the traditional finite-difference fine mesh approach. The advantages of using nodal methods coupled with integrated cross section generation systems are highlighted, especially with respect to data preparation, simplicity of use and the possibility of performing a great variety of reactor calculations subject to strict time limitations such as are required for the RERTR program.

Report Numbers:

E 1.99:anl/rertr/tm--20
E 1.99: conf-9409107--
conf-9409107--
anl/rertr/tm--20

Subject(s):

Nuclear Reactor Technology

Other Subject(s):

Note:

Published through SciTech Connect.
08/01/1997.
"anl/rertr/tm--20"
" conf-9409107--"
"DE98000036"
International meeting on reduced enrichment for research and test reactors, Williamsburg, VA (United States), 18-22 Sep 1994.
Mueller, E.Z.; Reitsma, F.

View MARC record | catkey: 14363029