Current American Society of Mechanical Engineers (ASME) nuclear codes and standards rely primarily on deterministic and mechanistic approaches to design. The design code is a separate volume from the code for inservice inspections and both are separate from the standards for operations and maintenance. The ASME code for inservice inspections and code for nuclear plant operations and maintenance have adopted risk-informed methodologies for inservice inspection, preventive maintenance, and repair and replacement decisions. The American Institute of Steel Construction and the American Concrete Institute have incorporated risk-informed probabilistic methodologies into their design codes. It is proposed that the ASME nuclear code should undergo a planned evolution that integrates the various nuclear codes and standards and adopts a risk-informed approach across a facility life-cycle — encompassing design, construction, operation, maintenance and closure.
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10th International Conference on Nuclear Engineering
April 14–18, 2002
Arlington, Virginia, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-3598-7
PROCEEDINGS PAPER
A Life-Cycle Risk-Informed Systems Structured Nuclear Code
Ralph S. Hill, III
Ralph S. Hill, III
Golder Associates, Inc., Las Vegas, NV
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Ralph S. Hill, III
Golder Associates, Inc., Las Vegas, NV
Paper No:
ICONE10-22739, pp. 661-669; 9 pages
Published Online:
March 4, 2009
Citation
Hill, RS, III. "A Life-Cycle Risk-Informed Systems Structured Nuclear Code." Proceedings of the 10th International Conference on Nuclear Engineering. 10th International Conference on Nuclear Engineering, Volume 4. Arlington, Virginia, USA. April 14–18, 2002. pp. 661-669. ASME. https://doi.org/10.1115/ICONE10-22739
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