Published March 2013 | Version v1
Journal article

ODS cladding fuel pins irradiation tests using the BOR-60 reactor

  • 1. Japan Atomic Energy Agency, Oarai, Ibaraki (Japan)
  • 2. Research Institute of Atomic Reactors, Joint Stock Company, Dimitrovgrad, Ulyanovsk region (Russian Federation)

Description

In order to confirm the irradiation behavior of ODS steels and thus judge their applicability to fuel claddings, fuel pin irradiation tests using 9Cr and 12Cr-ODS claddings developed by JAEA were conducted to burn-up of 11.9 at% and neutron dose of 51 dpa in the BOR-60. Superior properties of the ODS claddings concerning FCCI, dimensional stability under irradiation and so on were confirmed and indicated good application prospects for high burn-up fuel. On the other hand, anomalous irradiation behaviors, fuel pin failure and the microstructure change containing coarse and irregular precipitates, occurred in a part of the fuel pin with 9Cr-ODS cladding. This paper describes evaluation of the obtained irradiation data and the investigation results into the cause of the anomalous irradiation behaviors. (author)

Availability note (English)

Available from http://dx.doi.org/10.1080/00223131.2013.773165

Additional details

Identifiers

Publishing Information

Journal Title
Journal of Nuclear Science and Technology (Tokyo)
Journal Volume
50
Journal Issue
3-4
Journal Page Range
p. 387-399
ISSN
0022-3131

Optional Information

Notes
19 refs., 15 figs., 4 tabs.