PWR steam generator R&D in France: thermal-hydraulic and vibratory aspects

Abstract

Concomitant with the launching of the French pressurized water reactor (PWR) nuclear power program, a large research and development (R&D) effort was initiated, devoted to the steam generators (SGs). This program, managed cooperatively by Framatome, the SG designer and manufacturer; Electricité de France (EDF), the French electrical utility; and the Commissariat à l'Energie Atomique (CEA), the French Atomic Energy Commission, primarily responsible for nuclear research; was focused on four main objectives: 1. (1) To obtain a better understanding of the physical phenomena existing in these steam generators and leading to SG performance alterations or operating life reductions. 2. (2) To test and validate improved design solutions for the model 51 Framatome steam generator, which was the first one designed under Westinghouse license. 3. (3) To test and validate new Framatome SG designs. 4. (4) To test and validate new, high-performance design tools. This vast R&D program covers the following theses: • - SG thermal-hydraulics, • - SG tube vibration and wear, • - SG materials (production, corrosion, etc.), • - Primary and secondary fluid chemistry, • - SG technology (manufacturing processes, NDT, etc.), • - SG in-service inspection, and • - SG maintenance. These themes are too numerous to be dealt with in a single article. Consequently, the present article will focus on only the first two themes.