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Title: Influence of specimen size/type on the fracture toughness of five irradiated RPV materials

Abstract

The Heavy-Section Steel Irradiation (HSSI) Program had previously irradiated five reactor pressure vessel (RPV) steels/welds at fast neutron fluxes of about 4 to 8 x 10 11 n/cm 2/s (>1 MeV) to fluences from 0.5 to 3.4 10 19 n/cm 2 and at 288 °C. The unirradiated fracture toughness tests were performed by Oak Ridge National Laboratory with 12.7-mm and 25.4-mm thick (0.5T and 1T) compact specimens, while the HSSI Program provided tensile and 5 x 10-mm three-point bend specimens to SCK-CEN for irradiation in the in-pile section of the Belgian Reactor BR2 at fluxes > 10 13 n/cm 2/s and subsequent testing by SCK-CEN. The BR2 irradiations were conducted at about 2 and 4 x 10 13 n/cm 2/s with irradiation temperature between 295 °C and 300 °C (water temperature), and to fluences between 6 and 10 x 10 19n/cm 2. The irradiation-induced shifts of the Master Curve reference temperatures, ΔT 0, for most of the materials deviated from the embrittlement correlations much more than expected, motivating the testing of 5 x 10-mm three-point bend specimens of all five materials in the unirradiated condition to eliminate specimen size and geometry as a variable. Tests of the unirradiated small bendmore » specimens resulted in Master Curve reference temperatures, T 0, 25 °C to 53 °C lower than those from the larger compact specimens, meaning that the irradiation-induced reference temperature shifts, ΔT 0, were larger than the initial measurements, resulting in much improved agreement between the measured and predicted fracture toughness shifts.« less

Authors:
 [1];  [2]
  1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  2. National Inst. of Standards and Technology (NIST), Boulder, CO (United States)
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1224752
DOE Contract Number:
AC05-00OR22725
Resource Type:
Conference
Resource Relation:
Conference: 17. International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Ottawa, ON (Canada), 10-14 Aug 2015
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; SIZE; FRACTURE PROPERTIES; STEELS; FAST NEUTRONS; PHYSICAL RADIATION EFFECTS; MEV RANGE 01-10; PRESSURE VESSELS; SHAPE; TESTING; CORRELATIONS; EMBRITTLEMENT; TEMPERATURE RANGE 0400-1000 K; bend; compact; dpa; fracture toughness; irradiation; Master Curve; neutron fluence; reactor pressure vessel; specimen size

Citation Formats

Sokolov, Mikhail A, and Lucon, Enrico. Influence of specimen size/type on the fracture toughness of five irradiated RPV materials. United States: N. p., 2015. Web.
Sokolov, Mikhail A, & Lucon, Enrico. Influence of specimen size/type on the fracture toughness of five irradiated RPV materials. United States.
Sokolov, Mikhail A, and Lucon, Enrico. Thu . "Influence of specimen size/type on the fracture toughness of five irradiated RPV materials". United States. doi:. https://www.osti.gov/servlets/purl/1224752.
@article{osti_1224752,
title = {Influence of specimen size/type on the fracture toughness of five irradiated RPV materials},
author = {Sokolov, Mikhail A and Lucon, Enrico},
abstractNote = {The Heavy-Section Steel Irradiation (HSSI) Program had previously irradiated five reactor pressure vessel (RPV) steels/welds at fast neutron fluxes of about 4 to 8 x 1011 n/cm2/s (>1 MeV) to fluences from 0.5 to 3.4 1019 n/cm2 and at 288 °C. The unirradiated fracture toughness tests were performed by Oak Ridge National Laboratory with 12.7-mm and 25.4-mm thick (0.5T and 1T) compact specimens, while the HSSI Program provided tensile and 5 x 10-mm three-point bend specimens to SCK-CEN for irradiation in the in-pile section of the Belgian Reactor BR2 at fluxes > 1013 n/cm2/s and subsequent testing by SCK-CEN. The BR2 irradiations were conducted at about 2 and 4 x 1013 n/cm2/s with irradiation temperature between 295 °C and 300 °C (water temperature), and to fluences between 6 and 10 x 1019n/cm2. The irradiation-induced shifts of the Master Curve reference temperatures, ΔT0, for most of the materials deviated from the embrittlement correlations much more than expected, motivating the testing of 5 x 10-mm three-point bend specimens of all five materials in the unirradiated condition to eliminate specimen size and geometry as a variable. Tests of the unirradiated small bend specimens resulted in Master Curve reference temperatures, T0, 25 °C to 53 °C lower than those from the larger compact specimens, meaning that the irradiation-induced reference temperature shifts, ΔT0, were larger than the initial measurements, resulting in much improved agreement between the measured and predicted fracture toughness shifts.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Thu Jan 01 00:00:00 EST 2015},
month = {Thu Jan 01 00:00:00 EST 2015}
}

Conference:
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