Thermal hydraulics of nuclear reactor as a basis of reactor safety has a very important role in reactor design and control. The thermal-hydraulic analysis provides input data to the reactor-physics analysis, whereas the latter gives information about the distribution of heat sources, which is needed to perform the thermal-hydraulic analysis. In this study single heated channel model as a very f...

nuclear cross sections that determine core multiplication strongly depend on core temperature (e.g., the doppler, moderator density effects etc). on the other hand, since this heat is generated by the neutron flux in the reactor core, the temperature distribution in the core will depend heavily on its neutronic behavior. fuel centerline temperature could be the limiting constraint on reactor po...

The assessment process of large thermal-hydraulic computer codes aims at verifying their quality by comparing code predictions against experimental data gained by tests performed on scaled facilities. In the field of nuclear engineering only a few methods for quantitative assessment have been proposed. The objective of the study was to develop a Microsoft Excel add-in for accuracy evaluation of...

In the framework of the ASCHLIM project, a group of European experts in thermal hydraulic calculation has been clustered to evaluate the state of the art of CFD (Computational Fluid Dynamics) codes applied to ADS designs. The work of this group, supported by the Vth Framework Program of the European Union, has been focused on CFD analysis of the experiments that includes thermal hydraulic pheno...

SUBJECT: ISSUES ASSOCIATED WITH INDUSTRY-DEVELOPED THERMAL-HYDRAULIC CODES We are responding to the Staff Requirements Memorandum dated November 7, 2000 [Reference 1], in which the Commission requested the ACRS to provide a more detailed discussion on how the perceived weaknesses with industry-developed thermal-hydraulic codes may adversely affect the NRC's regulatory role and to provide more s...