Sensor performance for BWR dosimetry experiments
Description
In neutron dosimetry a combination of sensors (dosimeters) can be used for determining a flux density, fluence, and/or neutron spectrum in nuclear reactors. Each dosimeter is sensitive to a specific energy range, and, if desired, increased accuracy in the determination of a flux-spectrum can be achieved by the use of dosimeters that collectively embrace the significant neutron energy range. This report will briefly describe the selection, design, irradiation, post-irradiation handling, and quality control of neutron dosimeters utilized for thermal reactor surveillance neutron dosimetry at Browns Ferry Unit 3 (BF3). It will cover in-vessel, cavity, and drywell program work at BF3 through mid-1979. Photofission effects appear to be significant at pressure vessel surveillance locations
Additional details
Publishing Information
- ISBN
- 92-825-1867-1
- Imprint Title
- Dosimetry methods for fuels, cladding and structural materials
- Imprint Pagination
- 694 p.
- Journal Page Range
- p. 437-447.
- Report number
- EUR--6813(v.1)
Conference
- Title
- 3. ASTM-EURATOM symposium on reactor dosimetry.
- Dates
- 1 - 5 Oct 1979.
- Place
- Ispra, Italy.
INIS
- Country of Publication
- European Commission (EC), Brussels (Belgium)
- Country of Input or Organization
- European Commission (EC), Brussels (Belgium)
- INIS RN
- 12588900
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; FLUX DENSITY; NEUTRON DOSIMETRY; NEUTRON FLUENCE; NEUTRON FLUX; NEUTRON SPECTRA; PHOTOFISSION
- Descriptors DEC
- DOSIMETRY; FISSION; NUCLEAR REACTIONS; PHOTONUCLEAR REACTIONS; RADIATION FLUX; REACTORS; SPECTRA; WATER COOLED REACTORS; WATER MODERATED REACTORS