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U.S. Department of Energy
Office of Scientific and Technical Information

Pressure vessel fluence analysis and neutron dosimetry

Technical Report ·
OSTI ID:5718327
A review of the various methodologies used by industries and research institutes for reactor pressure vessel (RPV) fluence determination shows that most organizations employ an analysis sequence consisting of three steps. These include transport calculations, dosimetry measurements, and a statistical procedure to combine the calculations and measurements to arrive at a fluence value which has a smaller uncertainty than the original calculations. An accurate determination of damage fluence accumulated by the RPV as a function of space and time is essential in order to ensure the vessel integrity for both pressurized thermal shock transients and end-of-life considerations. The desired accuracy for neutron exposure parameters such as displacement per atom or neutron fluence (E > 1.0 MeV) is of the order of +-10% to +-15% (1sigma). these types of accuracies can only be obtained realistically by validation of the entire analysis sequence in benchmark experiments. This report identifies a standardized procedure based on benchmarked calculations, data, and dosimetry measurements, which could be used by organizations performing RPV fluence determinations. Another purpose of this report is to provide supporting documentation for any proposed regulatory guide on this subject. 33 refs., 8 figs., 10 tabs.
Research Organization:
Oak Ridge National Lab., TN (USA)
DOE Contract Number:
AC05-84OR21400
OSTI ID:
5718327
Report Number(s):
NUREG/CR-5049; ORNL/TM-10651; ON: TI88004475
Country of Publication:
United States
Language:
English