Dosimetry assessments for the reactor pressure vessel and core barrel in UK PWR plant
- Serco, Rutherford House, Quedgeley, Gloucester, Gl2 4NF (United Kingdom)
- VTT, Technical Research Centre of Finland, Otakaari 3 K, P.O. BOX 1000, Espoo, FI-02044 (Finland)
Specimens for the Sizewell B reactor pressure vessel (RPV) inservice steels surveillance program are irradiated inside eight capsules located within the reactor pressure vessel and loaded prior to commissioning. The periodic removal of these capsules and testing of their contents provides material properties data at intervals during the lifetime of the plant. Neutron activation measurements and radiation transport calculations play an essential role in assessing the neutron exposure of the specimens and RPV. Following the most recent withdrawal, seven capsules have now been removed covering nine cycles of reactor operation. This paper summarizes the dosimetry results of the Sizewell B surveillance program obtained to date. In addition to an overview of the calculational methodology it includes a review of the measurements. Finally, it describes an extension of the methodology to provide dosimetry recommendations for the core barrel and briefly discusses the results that were obtained. (authors)
- Research Organization:
- American Society for Testing and Materials - ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA, 19428-2959 (United States); European Working Group on Reactor Dosimetry - EWGRD, SCK.CEN, Mol (Belgium)
- OSTI ID:
- 22086940
- Report Number(s):
- INIS-US-13-ISRD-14-os1p-3; TRN: US13V0011045387
- Resource Relation:
- Conference: ISRD-14: 14. International Symposium on Reactor Dosimetry, Bretton Woods, NH (United States), 22-27 May 2011; Other Information: Country of input: France; 9 refs.
- Country of Publication:
- United States
- Language:
- English
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