Data survey and compilation of material property tables of irradiated stainless steel for evaluation of radiation effects on structural material properties of core internals in pressurized water reactors (Contract research)

Kasahara, Shigeki; Fukuya, Koji*; Fujimoto, Koji*; Fujii, Katsuhiko*; Chimi, Yasuhiro

JAEA-Review 2018-013, 171 Pages, 2019/01

JAEA-Review-2018-013.pdf:6.89MB

For structural integrity assessment of reactor internals of light water reactors, it is important to evaluate and predict the property changes of structural materials, based on existing data obtained from austenitic stainless steel irradiated with neutrons. Compilation of the data into tables is valuable for discussing the representative or the most probable values of the properties applied to the assessment. When the data compilation, the data must be distinguished clearly in consideration of different service conditions of core internals of pressurized water reactors (PWR) and boiling water reactors. Main objective of this work is to provide material property tables of irradiated austenitic stainless steel which will be applicable for assessment of structural integrity of core internals of PWRs. To compile the table, published literature reporting irradiated stainless steel data were surveyed and screened by considering the service conditions of PWRs. In addition to the data, various parameters for the data evaluation, e.g. chemical compositions and pre-treatments of the materials, irradiation and examination conditions, were extracted from the literature, and listed into tables.

The Effects of hydrogen addition on the corrosive conditions of PWR primary coolant under irradiation, 4; Direct and indirect effects of pH on ECP of stainless steel in the primary cooling water

Uchida, Shunsuke; Hata, Kuniki; Hanawa, Satoshi; Chimi, Yasuhiro

no journal, , 

The direct effects of hydrogen concentrations on the ECP were discussed in the previous presentation (the series #2). The parameters to determine ECP, e.g., pH and dose rate as well as hydrogen concentration, were different between in PWRs and BWRs. In the presentation, the direct and indirect effects of pH on ECP due to water radiolysis, surface properties and metallic ion solubilities are discussed. It was concluded that the corrosive conditions in the wide pH range which covered both PWR primary cooling water and BWR cooling water could be evaluated with a set of analysis codes for water radiolysis and ECP with applying the pH-dependent reaction constants.

Medical RI production using domestic nuclear infrastructures for self-sustenance, 2; Development of Mo/Tc production process

Nishikata, Kaori; Seki, Misaki; Fujita, Yoshitaka; Takeuchi, Tomoaki; Ide, Hiroshi; Tsuchiya, Kunihiko; Nasu, Takuya*; Takahashi, Shizuka*; Kobayashi, Kazuta*; Takaki, Naoyuki*

no journal, , 

Mo is the parent nuclide of Tc used for medical diagnostic. The Mo is produced by the fission method using the fission of uranium. However, the fission method requires a large investment in terms of nuclear regulation and nuclear non-proliferation. Therefore, in Japan, domestic production by the activation method using the neutron capture reaction of Mo is desired. In this study, R&D of Mo/Tc production by the activation method using PWRs was conducted. In this presentation, we report on the conceptual design of a dissolution treatment system for irradiation targets and a MoO recycling system using spent Mo solution was conducted. In addition, the cost of Tc production was evaluated and further study issues for realization are reported.