Evaluation of the use of nodal methods for MTR neutronic analysis
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.
- Research Organization:
- Argonne National Lab. (ANL), Argonne, IL (United States)
- OSTI ID:
- 567651
- Report Number(s):
- ANL/RERTR/TM-20; CONF-9409107-; ON: DE98000036; TRN: 98:003343
- Resource Relation:
- Conference: International meeting on reduced enrichment for research and test reactors, Williamsburg, VA (United States), 18-22 Sep 1994; Other Information: PBD: Aug 1997; Related Information: Is Part Of Proceedings of the 1994 international meeting on reduced enrichment for research and test reactors; PB: 427 p.
- Country of Publication:
- United States
- Language:
- English
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