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AbstractAbstract
[en] In this report application of the MCNP4B transport code in simulation of Heavy Water Zero Power Reactor (HWZPR) experiment in Nuclear Engineering Department of the Esfahan Research and Fuel Production Center (ERFPC) is verified. It should be noted that because MCNP4B code be able simulated HWZPR physically and geometrically and the lack of benchmark experiment data, this reactor is a suitable case to be simulated by MCNP4B. The continuous energy cross section data from ENDF/B-VI libraries and (α,β) thermal scattering treatment were used in calculations. The goal of the calculations were to determine the following parameters:The effective multiplication factor (Keff); Radial and axial flux distribution in core; Distribution of radial and axial cadmium ratio; This parameters is compared with experimental data and consistency and accuracy of the MCNP4B simulation HWZPR experiments established
Original Title
Shbihsazi-ye azmayeshat-e reaktor-e sefrghodrat-e ab-e sangin-e Esfahan (HWZPR) tavasot-e kod-e tarabord-e MCNP4B
Primary Subject
Source
2002; 5 p; Atomic Energy Organization of Iran, Nuclear Research Center for Agriculture and Medicine; Karaj (Iran, Islamic Republic of); 8. meeting of nuclear physicists and experts of Iran; Majmu'e maghalat-e hashtomin gerdehama-ee-ye fizikdanan va motekhasesan-e hast-e-ee-ye keshvar; Shahreza (Iran, Islamic Republic of); 20-21 Feb 2002; Available from Atomic Energy Organization of Iran
Record Type
Miscellaneous
Literature Type
Conference
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
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