| Heat source and fuel | Nuclear fission in solid fuel; in-core water serves as both coolant and moderator. | This page is limited to the route of dissolving nuclear fuel in salt. Different fuel cycles can be used, and the thorium route is just one of them; fission products will also be generated.Basis: S1, S2 |
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| Pressure and Leak Dynamics | The in-pile operating pressure is approximately 7 MPa. Safety analysis focuses on important scenarios such as pressure boundary failure, water loss, and obstruction of water replenishment. | The fuel salt circuit can operate close to atmospheric pressure, reducing the force driven by pressure release; however, there are still issues with high temperature, pumping, exhaust gas, and local pressure.Reference: S1 §3.1 / S2 Box 2.1 |
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| Reactor Shutdown and Residual Heat | Shutting down the reactor can stop the ongoing chain reaction, but it cannot immediately eliminate decay heat; reliable cooling and a final disposal of the heat are still required. | Residual heat must also be discharged. Some concepts use negative temperature feedback, natural circulation, or discharge of salt into a cooling container; applicability and reliability need to be verified according to the design.Basis: S1, S2 |
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| Mechanism of serious accidents | After the Fukushima earthquake, the reactors were shut down. The tsunami caused power and cooling failures, leading to severe fuel damage. High-temperature zirconium-steam reactions produced hydrogen, resulting in chemical explosions and radioactive releases. | The typical liquid fuel fluoride salt route changes the accident mechanisms of solid fuel rod melting and zirconium–steam interactions; it still requires analysis of salt leaks, cooling failures, reactive anomalies, off-gas, and chemical issues.Basis: S1, S2 |
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| Normal operating effluent | Controlled gaseous and liquid discharges from the operation of nuclear facilities must be treated, monitored, and subject to regulation. Normal operating conditions and accident conditions should not be treated as the same type of discharge. | Fuel salt, off-gas treatment systems, and related circuits contain radioactive substances; tritium may migrate and requires containment and monitoring. Low pressure does not automatically eliminate effluent.Basis: S1, S2 |
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| How pollution reaches the environment | After fuel is damaged, radioactive gases, particles, and contaminated water may breach barriers and enter air, soil, water, and food pathways. | Salt can chemically retain many fission products, potentially reducing some releases; effectiveness depends on nuclides, salt chemistry, and operating conditions. Leaked salt and volatile substances still need containment.Basis: S1, S2 |
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| Waste and decommissioning | Spent fuel and contaminated or activated equipment require long-term management; the Fukushima accident also left fuel fragments and a large amount of cleanup-related waste. | Waste salt, off-gas/chemical treatment waste, and irradiated equipment still need management. The quantity of waste, long-term radiotoxicity, and treatment burden differ across cycles and cannot all be classified as 'non-nuclear waste.'Basis: S1, S2 |
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| Magnitude and duration of environmental consequences | There are existing actual contamination, cleanup, and monitoring data. Impacts depend on nuclides, release amount, migration, exposure pathways, and protection; radioactive decay and environmental migration together affect the time scale. | Evaluation should be based on the inventory of radioactive material in the specific design, the proportion released in an accident, barrier capabilities, and the site. Without specifying these conditions, a unified impact radius or duration cannot be provided.Basis: S1, S2 |
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| Human living conditions and health | Evacuation, return, psychological stress, livelihood, trust, and long-term governance should all be considered. Attribution of radiation health effects depends on dose and epidemiological evidence, see the dedicated explanation below. | Potential contamination accidents may similarly affect evacuation, livelihood, and trust. Design advantages cannot replace emergency preparedness, information disclosure, occupational protection, and waste disposal responsibilities.Reference: S2, S3 |
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| Likelihood of contamination occurring | Fukushima was an accident at a specific site, time, reactor units, and disaster combination. BWR technology has a long operational record; a single accident cannot represent the probability for all modern nuclear power plants. | Low pressure and salt retention characteristics can reduce some accident-driving factors; the reliability of materials, monitoring, components, operation, and containment needs to be verified. The accident probability of a commercial reactor cannot be inferred from "the experimental reactor has operated."Basis: S1, S2, S4, S6 |
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| Comprehensive judgment: what is still lacking | Clearly identify the design, upgrades, site, operational management, radioactive inventory, and consistent evaluation criteria of the units being compared. | Also clearly specify the specific design and scale, then compare independent safety analysis, tests, and operational evidence. No percentages or "safety multiples" are provided here, because there is no probability study with consistent criteria to support it.Basis: Course comparison method based on the above information |
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