科技研发

R&D

COSINE

COSINE


严重事故堆芯机理分析程序(COSINE-SACM)
严重事故堆芯机理分析程序以压力容器内堆芯部件为研究对象,采用最佳估算分析方法和事故现象机理模型,可模拟严重事故工况下堆芯部件的加速氧化、熔化与重定位、裂变产物堆芯释放、熔池形成和蠕变断裂等严重事故现象机理和事故发展进程,该程序主要应用于核电厂严重事故分析和事故现象机理研究领域。
 

Severe Accident Core Mechanism Analysis Code (COSINE-SACM)

The COSINE-SACM code focuses on the behaviors of reactor core components under the condition of severe accident. The code adopts the best-estimate method and the mechanism models on severe accident phenomena. It is used to simulate an acceleration oxidation of the fuel assembly, core melting and relocation, fission products releasing from fuel assembly, formation phenomena of molten pool and creep rupture of structural components, etc. The code can be applied to the severe accident analysis in the nuclear power plant and the research on the mechanism of severe accident phenomena.

严重事故源项分析程序(COSINE-SAST)

严重事故源项分析程序以安全壳及其内部设备为计算对象,采用热工水力响应与裂变产物输运相耦合的方法,可模拟严重事故序列、源项分布以及专设安全设施动作后对事故进程的影响。该程序可用来处理一回路和安全壳内各种严重事故的物理过程,包括:放射性核素的释放和迁移、氢气的产生和燃烧、熔融物与混凝土反应等,主要应用于核电厂严重事故序列分析、源项分析和严重事故缓解措施分析等领域。


Severe Accident Source Term Analysis Code(COSINE-SAST)

The COSINE-SAST code focuses on the behaviors of reactor containment and its internal components under the condition of severe accident. The code adopts an couple method between thermal hydraulics and fission products transportation. It is used to analyze the severe accident sequences, fission products source term distribution and the influence of the engineering safety feature (ESF) on severe accident progress. The code can simulate the various severe accidents in the coolant loop and reactor containment, including the release and transfer of radioactive fission products, hydrogen generation and combustion, MCCI, etc. The code can be applied to the analyses on severe accident sequences, fission products source term and mitigation measure research on severe accident.