ORNL evaluation of the ORR-PSF metallurgical experiment and blind test

Conference · Sun Jan 01 00:00:00 EST 1984

OSTI ID:6513535

Stallmann, F W

A methodology is described to evaluate the dosimetry and metallurgical data from the two-year ORR-PSF metallurgical irradiation experiment. The first step is to obtain a three-dimensional map of damage exposure parameter values based on neutron transport calculations and dosimetry measurements which are obtained by means of the LSL-M2 adjustment procedure. Metallurgical test data are then combined with damage parameter, temperature, and chemistry information to determine the correlation between radiation and steel embrittlement in reactor pressure vessels including estimates for the uncertainties. Statistical procedures for the evaluation of Charpy data, developed earlier, are used for this investigation. The data obtained in this investigation provide a benchmark against which the predictions of the PSF Blind Test can be compared. The results of this investigation and the Blind Test comparison are discussed.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 6513535
• Report Number(s): CONF-840902-11; ON: DE85001546
• Resource Relation: Conference: 5. ASTM-Euratom symposium on reactor dosimetry, Geesthacht, F.R. Germany, 24 Sep 1984; Other Information: Portions are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
ORR REACTOR
PRESSURE VESSELS
DAMAGING NEUTRON FLUENCE
BENCHMARKS
CHARPY TEST
CORRELATIONS
PHYSICAL RADIATION EFFECTS
SIMULATION
STEELS
SURVEILLANCE
ALLOYS
CONTAINERS
DESTRUCTIVE TESTING
ENRICHED URANIUM REACTORS
IMPACT TESTS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS TESTING
MECHANICAL TESTS
NEUTRON FLUENCE
RADIATION EFFECTS
REACTORS
TANK TYPE REACTORS
TESTING
WATER COOLED REACTORS
WATER MODERATED REACTORS
220600* - Nuclear Reactor Technology- Research
Test & Experimental Reactors