You are being redirected because this document is part of your ASTM Compass® subscription.
    This document is part of your ASTM Compass® subscription.


    Neutron Dosimetry Overview for WWERs

    Published: 12 May 2018

      Format Pages Price  
    PDF (6.39 MB) 42 $25   ADD TO CART
    Complete Source PDF (32.31 MB) 494 $145   ADD TO CART

    Cite this document

    X Add email address send
      .RIS For RefWorks, EndNote, ProCite, Reference Manager, Zoteo, and many others.   .DOCX For Microsoft Word


    Neutron dosimetry is a mandatory part of the monitoring of irradiation conditions within the reactor pressure vessels (RPVs) of all type of reactors, including water-water energetic reactors (WWERs). The main experimental part is connected with the surveillance specimen programs because the determination of neutron fluence in each of the surveillance specimens is required for the evaluation of radiation damage in RPV materials. Ex-vessel (cavity) neutron dosimetry is practically mandatory for all WWERs because it serves as the basis for fitting results from calculations of neutron fluence in the RPV wall. In addition, retrospective neutron dosimetry in WWER RPVs is supported by a high content (approximately 1 wt.%) of niobium in the upper layer of the austenitic cladding on the inner RPV surface. This paper describes the main principles of experimental neutron dosimetry in WWER RPVs and some specific results for different types of their units and different surveillance specimen programs. Some discussion is also held regarding different approaches for neutron fluence determination, i.e., for a differential threshold energy equal to 0.5 MeV in WWER studies.


    WWER reactors, reactor pressure vessel, surveillance specimen program, embrittlement trend curve, codes and rules, surveillance specimen testing, surveillance test data evaluation, neutron fluence, WWER-440 reactors, WWER-1000 reactors, VERLIFE procedure

    Author Information:

    Brumovský, Milan
    ÚJV Řež a.s., Division of Integrity and Technical Engineering, Rez

    Marek, Milan
    Research Centre Rez sro., Division of Reactor Services, Rez

    Committee/Subcommittee: E10.02

    DOI: 10.1520/STP160320170038