Published 2014 | Version v1
Miscellaneous

A fundamental study on cesium transfer to sodium coolant

  • 1. Hokkaido Univ., Sapporo, Hokkaido (Japan)
  • 2. Central Research Institute of Electric Industry, Komae, Tokyo (Japan)

Description

An experimental study was achieved to evaluate the transfer behavior of cesium, which is one of the typical fission products, in the severe accident of sodium cooled fast reactors. In this study, the transfer characteristics of cesium to sodium coolant, which has a significant influence to the amount of the cesium reached to the cover gas of the reactor vessel in the core damage accident of sodium cooled fast reactors, was examined. Two series of experiments were performed to obtain the transfer characteristics of cesium to sodium coolant. The experimental results show the transfer rates of cesium to sodium pool vary in the range of 10E-3 to 10E-1 mol/(m2/min) with increasing cesium temperature from 200 degree C to 300 degree C. (author)

Part of:
Proceedings of the 10th international topical meeting on nuclear thermal hydraulics, operation and safety (NUTHOS-10)

Additional details

Publishing Information

Imprint Title
Proceedings of the 10th international topical meeting on nuclear thermal hydraulics, operation and safety (NUTHOS-10)
Imprint Pagination
2846 p.
Journal Page Range
9 p.

Conference

Title
10. international topical meeting on nuclear thermal hydraulics, operation and safety
Acronym
NUTHOS-10
Dates
14-18 Dec 2014
Place
Ginowan, Okinawa (Japan)

Optional Information

Notes
Available as USB Flash Memory Data in PDF format. Paper ID: NUTHOS10-1381.pdf; 2 refs., 8 figs., 5 tabs.