Abstract
The Advanced Test Reactor (ATR) is a light water reactor with aluminum-clad driver fuel. A primary mission of the ATR is to support the next generation of nuclear reactors. This support necessarily requires irradiation of advanced materials such as sodium, fuel salts, and metal eutectics. Irradiation of advanced materials in the ATR environment presents a challenge when completing accident analyses and demonstrating compliance to the Safety Analysis Report (SAR). Many advanced materials have the possibility to react with the ATR protective barriers such as the cladding or primary coolant system (PCS) boundary during postulated accident scenarios. Further, molten fuel experiments fall outside of the standard regulatory framework for dose consequence analyses. ATR is currently developing new safety analysis methods to support irradiation of advanced materials. The primary considerations for this development are 1) experiment containment design requirements, 2) primary coolant system response to an experiment containment failure, and 3) dose analyses for molten fuels.
| Original language | English |
|---|---|
| State | Published - 2024 |
| Event | 2024 ANS Annual Conference on Advanced Reactor Safety, ARS 2024 - Las Vegas, United States Duration: Jun 16 2024 → Jun 19 2024 |
Conference
| Conference | 2024 ANS Annual Conference on Advanced Reactor Safety, ARS 2024 |
|---|---|
| Country/Territory | United States |
| City | Las Vegas |
| Period | 06/16/24 → 06/19/24 |
Keywords
- 21 - SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
- 38 - RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEAR CHEMISTRY
- 11 - NUCLEAR FUEL CYCLE AND FUEL MATERIALS
- Advanced Reactor Safety
- Radiological Consequences
- Irradiation Experiments
- Material Interaction
- Structural Analysis
INL Publication Number
- INL/CON-24-77970
- 175988
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