Calculational tools to conduct experimental optimization in Tehran research reactor

Annals of Nuclear Energy

Volumn 26, Issue 17, 1999, Pages 1601-1610

  Khalafi, H ^a   Gharib, M ^b  

^a AMIRKABIR UNIVERSITY OF TECHNOLOGY   (Iran)

^b ATOMIC ENERGY ORGANIZATION OF IRAN   (Iran)

Author keywords

[No Author keywords available]

Indexed keywords

NEUTRON DETECTORS; NEUTRON IRRADIATION; RADIOISOTOPES; REACTOR CORES;

FLUX TRAP; NEUTRON FLUX MEASUREMENTS; NEUTRON SPECTRUM;

RESEARCH REACTORS;

EID: 0033216659     PISSN: 03064549     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0306-4549(99)00016-X     Document Type: Article

References (8)

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4. Briesmeister, J., 1993. General Monte Carlo N-particle Transport code, MCNP-4A. LA-12625.
5. Fowler, T. B. et al., 1971. Nuclear reactor core analysis code, CITATION. Rev. 2, ORNL-TM-2496, Oak Ridge national laboratory, Oak Ridge, Tenessee.
6. Khalafi, H., Gharib, M., 1998. Installation, calibration and application of incore miniature neutron detector in Tehran research reactor (TRR). Nuclear Instruments and Methods in Physics Research, vol. 413/2-3, Elsevier, pp. 374-378.
7. 99 production in TRIGA-II reactor. Seminar on applied research and service activities for research reactor operation, Copenhagen.
8. Mele, I., 1990. Optimization of TRIGA reactor operation using reactor calculations. J. Stefan Report.