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BS 4975:1990

Current
Current

The latest, up-to-date edition.

Specification for prestressed concrete pressure vessels for nuclear engineering
Available format(s)

Hardcopy , PDF

Language(s)

English

Published date

30-03-1990

Foreword
Committees responsible
Specification
Section one. General
1.1 Scope
1.2 Definitions
1.3 Basic considerations
1.4 Responsibilities
1.5 Information and requirements to be agreed and to
      be documented
1.6 Interpretation
Section two. Materials
2.1 Concrete
2.2 Reinforcement
2.3 Prestressing system
2.4 Liners (including supported penetration liners)
Section three. Design
3.1 General
3.2 PCPV structure
3.2.1 Design considerations
3.2.2 Analysis for service load conditions
3.2.3 Permissible stresses in concrete and
        reinforcement
3.2.4 Ultimate load analysis
3.3 Liners (including supported penetration liners)
3.3.1 General
3.3.2 Effects of irradiation
3.3.3 Design of liner
3.3.4 Design of ties and shear connectors
3.3.5 Design of corners
3.3.6 Design of penetration liners supported by
        concrete
Section four. Manufacture
4.1 Concrete
4.2 Reinforcement
4.3 Prestressing system
4.4 Liners (including supported penetration liners)
Section five. Inspection and tests
5.1 Concrete
5.2 Reinforcement
5.3 Prestressing system
5.4 Liners (including supported penetration liners)
Section six. Steel closures and unsupported penetrations
6.1 General
6.2 Materials
6.3 Design
6.4 Manufacture
6.5 Monitoring and inspection
6.6 Restrictors
Section seven. Insulation and cooling systems
7.1 General
7.2 Fault analysis
Section eight. Automatic pressure relief devices
8.1 Automatic pressure relief devices
Section nine. Testing and surveillance of completed
structure
9.1 Vessel proof test
9.2 Vessel leak test
9.3 Vessel vacuum test
9.4 Surveillance
Appendices
A. Simplified concepts of the development and analysis
    of stresses in a PCPV
B. Design and methods of analysis
C. Local stresses
D. Design limits for multiaxial compressive stresses in
    concrete
E. Ultimate load conditions
F. Corrosion protection of prestressing tendons
G. Grouting of ducted prestressing tendons
H. Effect of fast neutron irradiation on the properties
J. Effect of fast neutron irradiation on the mechanical
    properties of ferritic steels
K. Recommended practice for assessment of liners
    (including supported penetration liners) subject to
    fatigue
L. Construction of control charts for testing wire,
    strand and bar
M. Optional documentation for supply with the vessel
N. References
Tables
1. Principal compressive field stresses in concrete
2. Permissible stresses in steel reinforcement
Figures
1. Design limits for multiaxial compression
2. Typical fast neutron dose attenuation in a PCPV wall
3. Effect of irradiation on the dimensional changes of
    limestone aggregates, cement paste and a limestone
    aggregate concrete
4. Design fatigue curve for steels for temperatures
    up to and including 375 deg C
5. Construction of test fatigue curve

Design, construction, inspection and testing. Used for shielding and containing gas cooled nuclear reactors and are a form of civil engineering structure requiring particularly high integrity and ensured leak tightness.

1.1.1 This British Standard specifies the design, construction, inspection and testing of prestressed concrete pressure vessels (PCPV) for nuclear reactors, including components that are necessary to maintain the structural integrity and leaktightness of the vessels. However, such concrete pressure vessels are often closely integrated with the operation of the nuclear reactor and its auxiliary plant, and the various parts of the vessel may need to perform functions additional to the structural requirements of this standard.

1.1.2 The safety of concrete pressure vessels depends, firstly, on a correct assessment of the loadings likely to be applied to the vessel and, secondly, on the proper design of the vessel to accept these loadings. This standard covers only the second aspect, the first being the responsibility of the purchaser who has to meet any statutory or other regulations1).

1.1.3 The safety of concrete pressure vessels throughout their service lives also depends on proper operational procedures being adopted and adequate monitoring and inspection of the vessels during service life being carried out. As operational procedures are the responsibility of the operator they are not included in this standard. Monitoring and inspection are dealt with in 9.4.

1.1.4 Other components of the reactor pressure circuits, including those parts of the ancillary circuits that, for inspection, can be isolated from the primary circuit at any time without having to shut down the reactor, shall comply with the relevant British Standards and any additional requirements specified by the purchaser (see 1.5).

1.1.5 In addition to the definitive requirements, this standard also requires the items detailed in 1.5 to be documented. For compliance with this standard both the definitive requirements and the documented items need to be satisfied.

NOTE 1 Where the words “purchaser?? and “manufacturer?? occur in the text they should be taken to include representatives of the purchaser and manufacturer or inspectors mutually agreed upon.

NOTE 2 While this standard is based on current British practice which uses PCPVs in association with gas-cooled reactors, it is not intended to limit its use solely to reactors of this type. It is proposed to keep the standard under review, but it is realized that some of the requirements might be inapplicable to new developments and in such cases revised requirements should be specified by the purchaser.

NOTE 3 The titles of the publications referred to in this standard are listed on the inside back cover.

NOTE 4 Bibliographic references are identified by a letter and number in square brackets, e.g. [K4], and will be found either at the end of the relevant appendix or in Appendix N.

Committee
NCE/9
DevelopmentNote
Supersedes BS 4975(1973) & 87/77290 DC. (07/2005) Reviewed and confirmed by BSI, February 2011. (01/2011)
DocumentType
Standard
Pages
64
PublisherName
British Standards Institution
Status
Current
Supersedes

BS 5493:1977 Code of practice for protective coating of iron and steel structures against corrosion
BS 882:1992 Specification for aggregates from natural sources for concrete
BS 5328:1981 Methods for specifying concrete, including ready-mixed concrete
BS 4486:1980 Specification for hot rolled and hot rolled and processed high tensile alloy steel bars for the prestressing of concrete
BS 1370:1979 Specification for low heat Portland cement
BS 5896:1980 Specification for high tensile steel wire and strand for the prestressing of concrete
BS 600:2000 A guide to the application of statistical methods to quality and standardization
BS 3059:1958 Specification for steel boiler and superheater tubes
BS 8110-1:1985 Structural use of concrete Code of practice for design and construction
BS 4449:1997 Specification for carbon steel bars for the reinforcement of concrete
BS 4447:1973 Specification for the performance of prestressing anchorages for post-tensioned construction

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