Abstract
The RELAP5/MOD2 computer code has been extensively utilized in calculation of thermal-hydraulic sequences concerning the pressurized thermal shock safety issue in the Loviisa 1 nuclear power plant. The cases analyzed feature stuck-open pressurizer safety valve sequences, small hot-leg breaks, steam line breaks, and, in one case, a primary-secondary leakage. The main purpose of these analyses is to validate and compare the results from the full-scale Loviisa training simulator analyses.
The RELAP5 model is made to the detail allowed by the computer. It includes a description of primary and secondary circuits as well as modeling of the emergency core cooling and control systems.
Single-phase thermal stratification and mixing are essential phenomena when pressurized thermal shock sequences are analyzed. The capabilities of the large system analysis code to predict these phenomena in the reactor circuit are discussed
The RELAP5 model is made to the detail allowed by the computer. It includes a description of primary and secondary circuits as well as modeling of the emergency core cooling and control systems.
Single-phase thermal stratification and mixing are essential phenomena when pressurized thermal shock sequences are analyzed. The capabilities of the large system analysis code to predict these phenomena in the reactor circuit are discussed
| Original language | English |
|---|---|
| Pages (from-to) | 308-315 |
| Journal | Nuclear Technology |
| Volume | 90 |
| Issue number | 3 |
| DOIs | |
| Publication status | Published - 1990 |
| MoE publication type | A1 Journal article-refereed |