Vibration and wear in steam generator tubes following chemical cleaning. Semiannual report
Description
The Pacific Northwest Laboratory is studying the effects of increased tube/tube-support clearances in pressurized water reactor steam generators following chemical cleaning. Purpose is to provide the US Nuclear Regulatory Commission with criteria for evaluating licensees' specific proposals for chemical cleaning of steam generators. This report describes the test and data analysis plans and procedures for the flow and accelerated wear tests to be performed in a scale-model steam generator. The flow tests will establish the forcing boundary conditions, using clearances representing various conditions following chemical cleaning. The accelerated wear tests will determine the potential wear rates possible, based on the vibrations characterized in the flow tests. The overall project status, including work completed to date and tasks planned for the remainder of FY85, is also documented
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A03/MF A01 - GPO as TI85014157.
Files
Restricted
The record is publicly accessible, but files are restricted to users with access.
Additional details
Publishing Information
- Imprint Pagination
- 34 p.
- Report number
- NUREG/CR--4276
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 17007036
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Progress Report
- Descriptors DEI
- CLEANING; DATA PROCESSING; FLUID FLOW; MECHANICAL VIBRATIONS; PLANNING; PWR TYPE REACTORS; SCALE MODELS; STEAM GENERATORS; SUPPORTS; TUBES; WEAR
- Descriptors DEC
- BOILERS; ENRICHED URANIUM REACTORS; MECHANICAL STRUCTURES; POWER REACTORS; REACTORS; STRUCTURAL MODELS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- PNL--5477.