Abstract
Safety analyses in research reactors require the estimation of heat deposited in experiments and reactor structures after shutdown. The accurate assessment of the deposited energy across a reactor geometry better determines the heat removal requirements and ensures effective cooling. However, the development of experiment safety analyses on a case-by-case basis often proves to be effort and time-consuming. This article introduces a method based on the creation of a generic material irradiation database to expedite the process. The irradiation database is created by calculating the delayed heating in experiments of individual chemical elements. Then, the created database enables the quick calculation of the delayed heating of experiments of arbitrary material composition. This article showcases two applications to demonstrate the delayed heating calculation workflow and verify the generic material irradiation database method. These applications include a simple demonstration exercise and an Advanced Test Reactor experiment. The results display an overall good agreement between the generic material irradiation database method and reference values for a wide variety of experiments.
Original language | English (US) |
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Article number | 113634 |
Journal | Nuclear Engineering and Design |
Volume | 429 |
DOIs | |
State | Published - Dec 1 2024 |
Externally published | Yes |
Keywords
- ATR
- Delayed heating
- MCNP
- ORIGEN
- Research reactors
ASJC Scopus subject areas
- Nuclear and High Energy Physics
- General Materials Science
- Nuclear Energy and Engineering
- Safety, Risk, Reliability and Quality
- Waste Management and Disposal
- Mechanical Engineering