The Comparative Investigation and Calculation of Thermo-Neutronic Parameters on Two Gens II and III Nuclear Reactors with Same Powers
Abstract:Whereas in the third generation nuclear reactors,
dimensions of core and also the kind of coolant and enrichment
percent of fuel have significantly changed than the second
generation, therefore in this article the aim is based on a
comparative investigation between two same power reactors of
second and third generations, that the neutronic parameters of both
reactors such as: K∞, Keff and its details and thermal hydraulic
parameters such as: power density, specific power, volumetric heat
rate, released power per fuel volume unit, volume and mass of clad
and fuel (consisting fissile and fertile fuels), be calculated and
compared together. By this comparing the efficiency and
modification of third generation nuclear reactors than second
generation which have same power can be distinguished.
In order to calculate the cited parameters, some information
such as: core dimensions, the pitch of lattice, the fuel matter, the
percent of enrichment and the kind of coolant are used. For
calculating the neutronic parameters, a neutronic program entitled:
SIXFAC and also related formulas have been used. Meantime for
calculating the thermal hydraulic and other parameters, analytical
method and related formulas have been applied.
 Y. Tachibana, H. Sawahata, T. Iyoku, T. Nakazawa., Reactivity
control system of the high temperature engineering test reactor.
Nuclear Engineering and Design 233, 2004, pp.89-101.
 F. Zhao, K. Cheung, R. Yeung, Optimal power control system of a
research nuclear reactor. Nuclear Engineering and Design 219, 2003,
 J. Lamarsh, "Introduction to Nuclear Engineering (3 rd Ed) ";
Addison, Wesley, pp.35-80, 2001.
 J. Stacy, "Nuclear Reactor Physic"; JW, chapter (2, 3), 1999.
 E. Neil and M. Kazimi, "Nuclear Systems 1 Thermal Hydraulic
Fundamentals"; Hemisphere Publishing Corporation, pp.9-50, 1990.
 E. Wakil, "Nuclear Heat Transfer"; Hemisphere Publishing
Corporation, pp.103-109, 1991.
 J. Ben├¡tez, P. Mart├¡nez, H. Pérez, International cooperation on control
for safe operation of nuclear research reactors. Progress in Nuclear
Energy 46, 2005, pp.321-327.