LWR Pressure Vessel Surveillance Dosimetry Improvement Program. PSF startup experiments: Volume 2

Technical Report · Wed Jul 01 04:00:00 EDT 1992

OSTI ID:10168869

McElroy, W N ^[1]; Gold, R ^[2]; McGarry, E D ^[3]

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1. ed.; Consultants & Technology Services, Richland, WA (United States)
2. ed.; Metrology Control Corp., Richland, WA (United States)
3. ed.; National Inst. of Standards & Technology, Gaithersburg, MD (United States)

The metallurgical irradiation experiment at the Oak Ridge Research Reactor Poolside Facility (ORR-PSF) is one of the series of benchmark experiments in the framework of the Light Water Reactor Pressure Vessel Surveillance Dosimetry Improvement Program (LWR-PV-SDIP). The goal of this program is to test, against well-established benchmarks, the methodologies and data bases that are used to predict the irradiation embrittlement and fracture toughness of pressure and support structure steels. The prediction methodology includes procedures for neutron physics calculations, dosimetry and spectrum adjustment methods, metallurgical tests, and damage correlations. The benchmark experiments serve to validate, improve, and standardize these procedures. The results of this program are implemented in a set of ASTM standards on pressure vessel surveillance procedures. These, in turn, may be used as guides for the nuclear industry for the USNRC. To serve as a benchmark, a very careful characterization of the ORR-PSF experiment is necessary, both in terms of neutron flux-fluence spectra and of metallurgical test results. Statistically determined uncertainties must be given in terms of variances and covariancies to make comparisons between predictions and experimental results meaningful. This report supports analysis of the PSF Blind Test and provides experimental conditions, as-built documentation, and PSF physics-dosimetry results for the Startup, SSC-1, and SSC-2 experiments.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (United States). Div. of Engineering; Pacific Northwest Lab., Richland, WA (United States)
• Sponsoring Organization: Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 10168869
• Report Number(s): NUREG/CR--3320-Vol.2; WHC-EP--0204-Vol.2; ON: TI92019025
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100
210200
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900
36 MATERIALS SCIENCE
360103
BENCH-SCALE EXPERIMENTS
BWR TYPE REACTORS
DATA BASE MANAGEMENT
DOSIMETRY
EMBRITTLEMENT
FORECASTING
FRACTURE PROPERTIES
MECHANICAL PROPERTIES
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
BOILING WATER COOLED
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
PRESSURE VESSELS
PWR TYPE REACTORS
RADIATION EFFECTS
REACTOR SAFETY
STAINLESS STEELS
SURVEILLANCE
VALIDATION