Measurement of radiation levels in a BWR primary containment at power
Journal Article
·
· Radiation Protection Management; (United States)
OSTI ID:5587159
- Washington Public Power Supply System, Richland, WA (US)
This paper reports that during the start-up testing program at Washington Public Power Supply System's WNP-2 boiling water reactor, radiation levels had to be measured inside the primary containment (drywell) with the reactor operating at power in order to verify the integrity of the sacrificial shield and to estimate lifetime doses to critical electrical components within the drywell. These measurements were performed utilizing 144 comparisons of CaSO{sub 4}LiF TLDs mounted on polyethylene blocks spaced throughout containment. Average neutron energies in containment were estimated using a modification of the Bonner sphere method that permitted measurements to be performed without the need for personnel to enter hazardous areas--LiF extremity TLDs were used in place of the normal LiI(Eu) scintillation detector. The neutron energy and radiation level measurements indicated that the shield met its design criteria; however, higher-than-expected neutron dose rates were found that appeared to be caused by the large number of penetrations in the shield within the active core region.
- OSTI ID:
- 5587159
- Journal Information:
- Radiation Protection Management; (United States), Journal Name: Radiation Protection Management; (United States) Vol. 3:1; ISSN 0740-0640; ISSN RPMAE
- Country of Publication:
- United States
- Language:
- English
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BIOLOGICAL SHIELDS
BUILDINGS
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DESIGN
DOSEMETERS
DOSES
DOSIMETRY
ENRICHED URANIUM REACTORS
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