Published February 2011 | Version v1
Journal article

Measurement and calculations of 17N concentration in the main steam system of the BWR plant

  • 1. Hitachi-GE Nuclear Energy Ltd., Hitachi, Ibaraki (Japan)
  • 2. Chubu Electric Power Co., Inc., Nagoya, Aichi (Japan)
  • 3. Tokyo University, Division for Environment, Health and Safety, Tokyo (Japan)

Description

The radioactive concentration of 17N in the main steam system of the boiling water reactor (BWR) plant has been evaluated for the aging countermeasures and the planning of the plant decommissioning of the BWR. The neutron flux on the surface of the main steam pipe under the plant operation was measured by using a solid-state track detector. The flux due to 17N has been obtained by the Monte Carlo code calculations. It has been found that the concentration of 17N at the reactor pressure vessel outlet nozzle of the main steam pipe is approximately 3 Bq/cm3. The concentration has turned out to have small dependency on nuclear thermal power and to be almost common among the BWR plants. (author)

Availability note (English)

Available from http://dx.doi.org/10.15669/pnst.1.432

Additional details

Identifiers

Publishing Information

Journal Title
Progress in Nuclear Science and Technology
Journal Volume
1
Journal Page Range
p. 432-435
ISSN
2185-4823

Conference

Title
5. international symposium on radiation safety and detection technology
Acronym
ISORD-5
Dates
15-17 Jul 2009
Place
Kitakyushu, Fukuoka (Japan)

Optional Information

Notes
2 refs., 6 figs., 5 tabs.