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Swiss nuclear power and the case for long-term operation
Designed for 40 years but built to last far longer, Switzerland’s nuclear power plants have all entered long-term operation. Yet age alone says little about safety or performance. Through continuous upgrades, strict regulatory oversight, and extensive aging management, the country’s reactors are being prepared for decades of continued operation, in line with international practice.
Theron D. Marshall, Robert W. Hockenbury, John A. Honey, Lee C. CadWallader
Nuclear Technology | Volume 114 | Number 1 | April 1996 | Pages 84-96
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT96-A35225
Articles are hosted by Taylor and Francis Online.
Probabilistic risk assessment methodology is applied to generate an evaluation of the relative likelihood of safe recovery following selected pressurized water reactor (PWR) design basis accidents for a Russian V213 nuclear power reactor. U.S.-designed PWRs similar to the V213 are used for reference and comparison. This V213 risk assessment is based on comparison analyses of the following aspects: accident progression event tree success paths for typical PWR accident initiating events, safety aspects in reactor design, and perceived performance of reactor safety systems. The four initiating events considered here were taken from a U.S. Nuclear Regulatory Commission summary report on severe accident risk: loss of offsite power with station blackout, large-break loss-of-coolant accident (LOCA), medium-break LOCA, arid small-break LOCA. The success probabilities for the V213 reaching a non-core-damage state after the onset of the selected initiating events are calculated for two scenarios: (a) using actual component reliability datafrom U. S. PWRs and (b) assuming common component reliability data. U.S. PWR component reliability data are used because of the unavailability of such data for the V213 at the time of the analyses. While the use of U.S. PWR data in this risk assessment of the V213 does strongly infer V213 comparability to U.S. plants, the risk assessment using common component reliability does not have such a stringent limitation and is thus a separate scoping assessment of the V213 engineered safety systems. The results of the analyses suggest that the V213 has certain design features that significantly improve the reactor’s safety margin for the selected initiating events and that the V213 design has a relative risk of core damage for selected initiating events that is at least comparable to U.S. PWRs. It is important to realize that these analyses are of a scoping nature and may be significantly influenced by important risk factors such as V213 operator training, quality control, and maintenance procedures. Additionally, the analyses make no implications as to the effects of the selected initiating events on the health and safety of the public.