Category Archives: Materials’ ageing and degradation in. light water reactors

Overview of ageing and degradation issues in light water reactors (LWRs)

K. L. MURTY, North Carolina State University, USA and K. RAMASWAMY, Bhabha Atomic Research Center, India DOI: 10.1533/9780857097453.1.3 Abstract: A typical light water reactor (LWR) has components like the clad, the internals, the reactor pressure vessel (RPV), the heat exchanger tubes, etc., made from different materials. Some of these components experience pressure and temperature effects while others experience an additional […]

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Basic design features of the VVER-440

The V-179, V-230 and V-213 types of VVER plants are equipped with a six-loop VVER-440 reactor. In each loop, there are main isolating valves (MIV) on the cold and hot legs, one main circulation pump (MCP) per loop and horizontal steam generators (SG). The pressurizer, with safety valves, is connected to the primary loop. The two generations of the VVER-440 […]

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Synergies: safety upgrading, reconstructions and power up-rate

There is a synergy between the possibility of LTO and different plant actions and measures implemented for safety upgrading, power up-rate, improving reliability and plant programmes. Implementation of the safety upgrading programme for ensuring the compliance with national and international requirements is a precondition for LTO. At the same time, safety is the most important aspect of public acceptance. The […]

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Degradation mechanisms and materials ageing issues in nuclear steam supply systems (NSSS)

As shown in Tables 1.2 and 1.3, we note that a large number of materials are used for various components in nuclear power systems. It is important to state here that relatively large structures can only be fabricated using welded joints and the designers need to account for the varied properties of the dif­ferent materials and their welds; often welds […]

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