Radiation resistance of high-density uranium—molybdenum dispersion fuel for nuclear research reactors

Author:

Vatulin A. V.,Morozov A. V.,Suprun V. B.,Petrov Yu. I.,Trifonov Yu. I.

Publisher

Springer Science and Business Media LLC

Subject

Nuclear Energy and Engineering

Reference14 articles.

1. G. Hofman, “Irradiation behavior of high uranium density-low enriched — U—Mo research reactor fuel,” in: Proceedings of the IAEA Consultancy on Development of High Density U—Mo Dispersion Fuels, IAEA, Vienna (2003).

2. M. Meyer, G. Hofman, S. Hayes, et al., “Low temperatures irradiation behavior of uranium— molybdenum alloy dispersion fuel,” J. Nucl Mater., 304, 221–336 (2002).

3. G. Hofman, J. Snelgrove, S. Hayes, et al., “Progress in postirradiation examination and analysis of low enriched U—Mo research reactor fuels,” in: Transactions of the 7th International Topical Meeting on RRFM, France, March 9–12, 2003, pp. 43–50.

4. G. Hofman, Y. Kim, M. Finlay, et al., “Recent observations at the postirradiation examination of low entriched U—Mo miniplates irradiated to high burnup,” in: Transactions of the 8th International Topical Meeting on RRFM, Germany, March 21–24, 2004, pp. 53–58.

5. A. V. Vatulin, A. V. Morozov, V. B. Suprun, et al., “High-density U—Mo fuel for research reactors,” Metallovedenie i Termicheskaya Obrabotka Metallov, No. 11, 35–50 (2004).

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