Effects of shutdown chemistry on steam generator radiation levels at Point Beach Unit 2. Interim report
Description
A refueling shutdown chemistry test was conducted at a PWR, Point Beach Unit 2. The objective was to yield reactor coolant chemistry data during the cooldown/shutdown process which might establish a relationship between shutdown chemistry and its effects on steam generator radiation fields. Of particular concern were the effects of the presence of hydrogen in the coolant as contrasted to an oxygenated coolant. Analysis of reactor coolant samples showed a rapid soluble release (spike) in Co-58, Co-60, and nickel caused by oxygenation of the coolant. The measurement of radioisotope specific activities indicates that the material undergoing dissolution during the shutdown originated from different sources which had varying histories of activation. The test program developed no data which would support theories that oxygenation of the coolant while the steam generators are full of water contributes to increased steam generator radiation levels
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A04/MF A01 as DE82904982.
Files
Additional details
Publishing Information
- Imprint Pagination
- 64 p.
- Report number
- EPRI-NP--860
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 14720498
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- POINT BEACH-2 REACTOR; RADIOACTIVITY; REACTOR SHUTDOWN; STEAM GENERATORS; WATER CHEMISTRY
- Descriptors DEC
- BOILERS; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WATER TREATMENT