APA (7th ed.) Citation

U.S. Nuclear Regulatory Commission. Division of Fuel, Engineering, and Radiological Research, Pacific Northwest National Laboratory (U.S.), & Gosselin, S. R. (2007). Fatigue crack flaw tolerance in nuclear power plant piping: A basis for improvements to ASME code section XI Appendix L. U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Division of Fuel, Engineering and Radiological Research.

Chicago Style (17th ed.) Citation

U.S. Nuclear Regulatory Commission. Division of Fuel, Engineering, and Radiological Research, Pacific Northwest National Laboratory (U.S.), and S. R. Gosselin. Fatigue Crack Flaw Tolerance in Nuclear Power Plant Piping: A Basis for Improvements to ASME Code Section XI Appendix L. Washington, DC: U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Division of Fuel, Engineering and Radiological Research, 2007.

MLA (9th ed.) Citation

U.S. Nuclear Regulatory Commission. Division of Fuel, Engineering, and Radiological Research, et al. Fatigue Crack Flaw Tolerance in Nuclear Power Plant Piping: A Basis for Improvements to ASME Code Section XI Appendix L. U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Division of Fuel, Engineering and Radiological Research, 2007.