Prestressing in nuclear power plants anchor lift-off measuring system for 37 T 15 tendons
Creators
- 1. Asoc. Nuclear Asco, Civil Eng Dept, Asco NPP, Tres Torres 7, Barcelona 08017 (Spain)
Description
The Asco Nuclear Power Plant is composed of two 930 MW PWR units. The external wall of the Containment Building in each unit is made of prestressed concrete. The Pre-stressing System, a Freyssinet technology using 37 T 15 tendons, is of the non-adhering type (sheathing is filled with grease). This technique allows to verify the design conditions of the prestressing design directly through the tendons by means of periodical inspections carried out during the whole life of the structure. These inspections take place three times in the first five years and afterwards, once every five years. One of the objectives of these inspections is to measure the prestressing force that the type 37 T 15 tendons apply on the structure. The measurement of the force is made by the same KC 1000 jack used in the pre-tensioning with a capacity of 1000 ton which acts on the tendon anchorage, increasing the outside tendon tension progressively up to reaching the block anchorage lift-off from its support plate. The lift-off force applied by the jack is the internal tension developed by the tendon. The problem is to determine the exact moment when the tendon anchorage block 'lift-off' takes place. In the 1980's decade, the anchorage block lift-off was determined by inserting thin shims. The insertion of one of these shims between the support plate and the anchorage block indicated the separation. Simultaneously, the necessary force applied by the jack to overcome the tendon compressive action on the structure was registered. This force, extrapolated to a zero separation, was assumed to be acting on the anchorage. This procedure had the inconvenient of a lack of accuracy in determining the physical phenomena. The system used at the present to measure the lift-off force consists basically in taking continuous elongation and jacking force data by means of a computerized system. The present work describes this new system, resulting from 15 years of experience in measuring the lift-off forces in the prestressing system
Additional details
Publishing Information
- Imprint Title
- Proceedings of the joint WANO/OECD-NEA workshop on pre-stress loss in NPP containments
- Imprint Pagination
- 380 p.
- Journal Page Range
- p. 223-234
- Report number
- NEA-CSNI-R--1997-9
Conference
- Title
- Joint WANO/OECD-NEA workshop on pre-stress loss in NPP containments
- Dates
- 25-26 Aug 1997
- Place
- Poitiers (France)
INIS
- Country of Publication
- Nuclear Energy Agency of the OECD (NEA)
- Country of Input or Organization
- Nuclear Energy Agency of the OECD (NEA)
- INIS RN
- 43058920
- Subject category
- S42: ENGINEERING; S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCURACY; ANCHORS; CABLES; COMPUTERIZED CONTROL SYSTEMS; CONTAINMENT; MEASURING INSTRUMENTS; MEASURING METHODS; MONITORING; NEA; NUCLEAR POWER PLANTS; PRESTRESSED CONCRETE; PWR TYPE REACTORS; REACTOR MONITORING SYSTEMS; RELAXATION LOSSES; SPAIN; STRAIN RATE; STRAINS; STRESS ANALYSIS
- Descriptors DEC
- BUILDING MATERIALS; COMPOSITE MATERIALS; CONCRETES; CONTROL SYSTEMS; DEVELOPING COUNTRIES; ENERGY LOSSES; ENRICHED URANIUM REACTORS; EUROPE; INTERNATIONAL ORGANIZATIONS; LOSSES; MATERIALS; NUCLEAR FACILITIES; OECD; ON-LINE CONTROL SYSTEMS; ON-LINE SYSTEMS; POWER PLANTS; POWER REACTORS; REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WESTERN EUROPE
Optional Information
- Secondary number(s)
- OCDE-GD--97-225