In this study, according to the structure and material characteristics of the metal-matrix
dispersed plate-type fuel assembly, a series of mathematical and physical models were …

This paper proposes the preliminary emergency core cooling scheme for Tsinghua High
Flux Reactor. According to the thermohydraulic characteristics of high flux reactors, forced …

Covering the wide range of reactor safety analysis of power reactors, consisting of leak and
transients, the thermohydraulic code ATHLET is being developed by the Gesellschaft for …

针对中国先进研究堆(CARR) 的具体特点开发了堆芯多通道热工水力计算程序ECARR.
通过对全堆芯的数值模拟, 得到了堆芯流量分配和非对称冷却条件下板状燃料元件的温度场 …

A multi-dimensional computational fluid dynamics (CFD) one-phase model to simulate the in-
core coolant circuit of a pressurized heavy water reactor (PHWR) of a nuclear power plant …

A full-scale ATHLET system model for the Syrian miniature neutron source reactor (MNSR)
has been developed. The model represents all reactor components of primary and …

A two-group, three-dimensional diffusion theory based methodology coupled with one-
dimensional single-phase heat transfer calculations has been developed for the transient …

A system model of the Advanced Neutron Source Reactor (ANSR) has been developed and
used to perform conceptual safety analyses. To better represent thermal-hydraulic behavior …

The plate-shaped fuel element has good heat transfer characteristics, high average power
density of the core, and low temperature of the fuel core, which is beneficial to improve the …

A multi-channel model steady-state thermal-hydraulic analysis code was developed for the
China Advanced Research Reactor (CARR). By simulating the whole reactor core, the …