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Predicting volume swelling of structural materials in nuclear reactors underhigh-dose neutron irradiations based on existing low-dose experiments orirradiation data with high-dose-rate energetic particles has been along-standing challenge for safety evaluation and rapidly screeningirradiation-resistant materials in nuclear energy systems. Here, we build anAdditional Defect Absorption Model that describes the irradiation-inducedswelling effects produced by energetic electrons, heavy-ions, and neutrons byconsidering additional defect sinks inherent in the irradiation process. Basedon this model, we establish quantitative methods to predict high-dose swellingfrom low-dose behavior and obtain the equivalent irradiation dose for differentenergetic particles when the dose rates differ by several orders of magnitude.Furthermore, we propose a universal parameter to characterize the swellingresistance of various alloys and predict their radiation tolerances underdifferent radiation conditions. This work provides quantitative predictionmethods for evaluating irradiation-induced swelling effects of structuralmaterials, which is critical to the safety and material development foradvanced nuclear reactors.

Model-based quantitative methods to predict irradiation-induced swelling in alloys