Fast Reactor Technology for Energy Security: Challenges for Materials Development

Abstract

Fuel cycle cost of sodium cooled fast reactors is strongly dependent on the performance of core structural materials, i.e., clad and wrapper materials of the fuel subassembly, which are subjected to intense neutron irradiation during service, that leads to unique materials problems like void swelling, irradiation creep and helium embrittlement. In order to increase the burnup of the fuel and thereby reduce the fuel cycle cost, it is necessary to employ materials which have high resistance to void swelling as well as better high temperature mechanical properties. The Indian fast reactor program began with the commissioning of the 40 MW t Fast Breeder Test Reactors (FBTR). The core structural material of FBTR is 20% cold worked 316 austenitic stainless steel (SS). For the 1250 MW t Prototype Fast Breeder Reactor which is nearing completion of construction, 20% cold-worked alloy D9 (15Cr-15Ni-Ti) has been selected as the clad and wrapper material. The target burnup is 100 GWd/t. Advanced austenitic stainless steel called as IFAC-1 SS and oxide dispersion strengthened martensitic steels have been developed as future materials for achieving higher burnup. Type 316 SS and its modified versions are used as the major high temperature structural materials for out-of-core permanent components. Ferritic-martensitic steels are selected for steam generator applications. This paper reviews the unique problems in fast reactors and illustrates the global progress in developing advanced structural materials for fast reactors in the context of the Indian nuclear programme.

Enhancing Piping System Reliability Through Material Upgrades and ANN-Based Damage Parameter Estimation

“…Meireles et al [11] provide a comprehensive review of the industrial applicability of artificial neural networks, emphasizing their role in modern reliability engineering. Additionally, [12] documents proceedings from a seminar on Materials Research and Development for Prototype Fast Breeder Reactors (PFBR), emphasizing the importance of materials research in advanced reactor systems. Jones [13] focuses on mitigating corrosion problems in LWRs through changes in water chemistry, underlining the significance of chemistry alterations in combating corrosion issues.…”

“…Due to their suitable high-temperature properties, which include high creep strength, resistance to low cycle fatigue and creep-fatigue interactions, and good resistance to environmentally sensitive cracking, austenitic stainless steels are preferred as the primary structural materials in a variety of industries. Their selection is supported by the availability of code data on mechanical parameters and their better weldability [12].…”

The Development of Alumina Forming Austenitic Alloy for Core Application in Advanced Nuclear Reactors

“…Austenitic stainless steel shows good high temperature strength, excellent oxidation resistance, especially, good ductility and workability, thus is a kind of important high temperature structural material application in energy industry [1][2][3]. For example, 316 Ti and D9 (15-15Ti) austenitic steels have been using as fuel cladding materials in current sodium cooled reactor, 310 type austenitic steel is promising for core application in super-critical water cooled reactors (SCWR), austenitic steel is also potential for fuel cladding application in accident-tolerant fuel and for blanket application in the fusion reactors [4][5][6][7].…”