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ASTM International - ASTM E1035-85(1996)

Standard Practice for Determining Radiation Exposures for Nuclear Reactor Vessel Support Structures

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Organization: ASTM International
Publication Date: 1 January 1996
Status: inactive
Page Count: 2
ICS Code (Nuclear power plants. Safety): 27.120.20
scope:

1.1 This practice covers procedures for monitoring the neutron radiation exposures experienced by ferritic materials in nuclear reactor vessel support structures located in the vicinity of the active core. This practice includes guidelines for:

1.1.1 Selecting appropriate dosimetric sensor sets and their proper installation in reactor cavities.

1.1.2 Making appropriate neutronics calculations to predict neutron radiation exposures.

1.2 This practice is applicable to all pressurized water reactors whose vessel supports will experience a lifetime neutron fluence (E > 1 MeV) that exceeds 1 X 17 neutrons/cm2 or 3.0 X 10-4 dpa.2 (See Terminology E170.)

1.3 This standard may involve hazardous materials, operations, and equipment. This standard does not purport to address all of the safety problems associated with its use. It is the responsibility of whoever uses this standard to consult and establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

Document History

June 1, 2018
Standard Practice for Determining Neutron Exposures for Nuclear Reactor Vessel Support Structures
1.1 This practice covers procedures for monitoring the neutron radiation exposures experienced by ferritic materials in nuclear reactor vessel support structures located in the vicinity of the active...
January 1, 2013
Standard Practice for Determining Neutron Exposures for Nuclear Reactor Vessel Support Structures
3.1 Prediction of neutron radiation effects to pressure vessel steels has long been a part of the design and operation of light water reactor power plants. Both the federal regulatory agencies (see...
November 1, 2008
Standard Practice for Determining NeutronExposures for Nuclear Reactor Vessel Support Structures
1.1 This practice covers procedures for monitoring the neutron radiation exposures experienced by ferritic materials in nuclear reactor vessel support structures located in the vicinity of the active...
June 10, 2002
Standard Practice for Determining NeutronExposures for Nuclear Reactor Vessel Support Structures
Prediction of neutron radiation effects to pressure vessel steels has long been a part of the design and operation of light water reactor power plants. Both the federal regulatory agencies (see 2.2)...
ASTM E1035-85(1996)
January 1, 1996
Standard Practice for Determining Radiation Exposures for Nuclear Reactor Vessel Support Structures
1.1 This practice covers procedures for monitoring the neutron radiation exposures experienced by ferritic materials in nuclear reactor vessel support structures located in the vicinity of the active...
January 1, 1990
Standard Practice for Determining Radiation Exposures for Nuclear Reactor Vessel Support Structures
A description is not available for this item.
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