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March 22, 2019
Published Online: 2019-03-22
Published in Print: 2019-03-18
© 2019, Carl Hanser Verlag, München
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- Technical Contributions/Fachbeiträge
- New research reactor protection system
- Ultimate response guideline strategy evaluation for Maanshan power plant
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- Simulation and analysis of the Loss of Flow Accident (LOFA) scenarios for an open pool type research reactor by using the RELAP5/MOD3.2 code
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Articles in the same Issue
- Contents/Inhalt
- Contents
- Technical Contributions/Fachbeiträge
- New research reactor protection system
- Ultimate response guideline strategy evaluation for Maanshan power plant
- Application of two alternative shutdown severe accident management guideline (SSAMG) entry conditions for CPR1000
- Simulation and analysis of the Loss of Flow Accident (LOFA) scenarios for an open pool type research reactor by using the RELAP5/MOD3.2 code
- Numerical study on cut-off diameter of aerosol particle for filtered containment venting system in nuclear power plant
- Reanalysis of environmental qualification radiation parameters for Kuosheng nuclear power plant
- Effect of reactor operator intervention during unprotected LOFA in a typical MTR
