| 论文简介 |
The China advanced research reactor (CARR) being built in Beijing, China, is a multipurpose
research reactor for a variety of fields. Theoretical calculation of thermal hydraulic characteristics
of CARR is presented in this paper. The theoretical analysis consists of initial
steady and transient accidental analyses. Point reactor neutron kinetics model with six groups
of delayed neutron is adopted for the solution of reactor power. All possible flow and heat
transfer conditions are considered and the corresponding optional models are supplied in
the theoretical calculations. A new simple and convenient model is proposed for the resolution
of the transient behaviors of main pump instead of the complicated four-quadrant model.
Gear method and Adams predictor–corrector method are adopted alternately for a better
solution to such ill-conditioned differential equations corresponding to detail process. The initial
multi-channel analysis shows that the effects of geometrical size on flow distribution play
dominant role and the effects of core power distribution may be neglected. The temperature
fields of fuel elements under asymmetrical cooling condition are also obtained, which are
the bases for further study on transient-induced stress analysis, etc. Accidental analyses show
that the activity of emergency cooling system apparently reduces the peak temperatures of fuel
and coolant, peak quality and other operation parameters. Thus it effectively ensures the safety in operation of CARR. Because of the adoption of modular programming techniques,
this code is expected to be applied to accidental analysis of other types of reactors by easily
modifying the corresponding function modules. Also, this code is expected to be validated
against experimental data. |
(创新港)
