Results of reliability test program on light water reactor piping
- 31 December 1994
- journal article
- Published by Elsevier in Nuclear Engineering and Design
- Vol. 153 (1) , 71-86
- https://doi.org/10.1016/0029-5493(94)90022-1
Abstract
No abstract availableKeywords
This publication has 11 references indexed in Scilit:
- Evaluation of LBB in Piping Considering Multiple Fatigue Crack Growth.TRANSACTIONS OF THE JAPAN SOCIETY OF MECHANICAL ENGINEERS Series A, 1992
- Measurement of leak-rate through fatigue-cracks in pipes under four-point bending and BWR conditionsInternational Journal of Pressure Vessels and Piping, 1990
- Temperature increase on target due to jet impingement under BWR/PWR loss of coolant accident conditionsNuclear Engineering and Design, 1988
- Experimental and analytical studies of pipe whip tests under PWR LOCA conditionsNuclear Engineering and Design, 1987
- Jet discharging test under BWR and PWR Loss-of-Coolant Accident Conditions.Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan, 1987
- Growth evaluation of fatigue cracks from multiple surface flaws, (II) Fatigue test result of straight pipes containing surface flaws and comparison with analytical fatigue behavior evaluation.Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan, 1986
- Growth evaluation of fatigue cracks from multiple surface flaws. (III) Fatigue test result of bend pipes containing surface flaws and comparison with analytical fatigue behavior evaluation.Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan, 1986
- Growth evaluation of fatigue cracks from multiple surface flaws, (I) Fatigue behavior of flat plate specimen of Type 304L stainless steel with surface cracks and evaluation of crack growth behavior.Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan, 1985
- Calculation of JAERI's jet discharge experiment by KfK's code DRIX-2DNuclear Engineering and Design, 1984
- The Two-Phase Critical Discharge of Initially Saturated or Subcooled LiquidNuclear Science and Engineering, 1970