LWR Pressure Vessel Surveillance Dosimetry Improvement Program

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

OSTI ID:7232898

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

---

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: NRC; Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 7232898
• 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 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
ALLOYS
BENCH-SCALE EXPERIMENTS
BWR TYPE REACTORS
CONTAINERS
DATA BASE MANAGEMENT
DOSIMETRY
EMBRITTLEMENT
ENRICHED URANIUM REACTORS
FORECASTING
FRACTURE PROPERTIES
HIGH ALLOY STEELS
IRON ALLOYS
IRON BASE ALLOYS
MANAGEMENT
MECHANICAL PROPERTIES
POWER REACTORS
PRESSURE VESSELS
PWR TYPE REACTORS
RADIATION EFFECTS
REACTOR SAFETY
REACTORS
SAFETY
STAINLESS STEELS
STEELS
SURVEILLANCE
TESTING
THERMAL REACTORS
VALIDATION
WATER COOLED REACTORS
WATER MODERATED REACTORS