Published 2011 | Version v1
Miscellaneous

Retrospective dosimetry analyses of reactor vessel cladding samples

  • 1. Battelle Pacific Northwest National Laboratory, Richland, WA 99352 (United States)
  • 2. Westinghouse Electric Company, Cranberry Twp., PA 16066 (United States)

Description

Reactor pressure vessel cladding samples for Ringhals Units 3 and 4 in Sweden were analyzed using retrospective reactor dosimetry techniques. The objective was to provide the best estimates of the neutron fluence for comparison with neutron transport calculations. A total of 51 stainless steel samples consisting of chips weighing approximately 100 to 200 mg were removed from selected locations around the pressure vessel and were sent to Pacific Northwest National Laboratory for analysis. The samples were fully characterized and analyzed for radioactive isotopes, with special interest in the presence of Nb-93m. The RPV cladding retrospective dosimetry results will be combined with a re-evaluation of the surveillance capsule dosimetry and with ex-vessel neutron dosimetry results to form a comprehensive 3D comparison of measurements to calculations performed with 3D deterministic transport code. (authors)

Availability note (English)

Available from the INIS Liaison Officer for France, see the INIS contacts section of the INIS website for current contact and E-mail addresses: http://www.iaea.org/INIS/contacts/

Additional details

Publishing Information

Imprint Pagination
7 p.
Report number
INIS-US--13-ISRD-14-os3p-3

Conference

Title
14. International Symposium on Reactor Dosimetry
Acronym
ISRD-14
Dates
22-27 May 2011
Place
Bretton Woods, NH (United States)

Optional Information

Notes
2 refs.