Influence of neutron irradiation damage on the equilibrium properties of the polycrystallineBi1.8Pb0.3Sr2Ca2Cu3O10superconductor

1995 ◽  
Vol 51 (13) ◽  
pp. 8551-8559 ◽  
Author(s):  
J. G. Ossandon ◽  
J. R. Thompson ◽  
Y. C. Kim ◽  
Yang Ren Sun ◽  
D. K. Christen ◽  
...  
Keyword(s):  
Neutron Irradiation ◽  
Irradiation Damage

Effects of Neutron Irradiation on the Mechanical and Electromagnetic Properties of Reactor Pressure Vessel Steels

2017 ◽  
Author(s):  
Li Chengliang ◽  
Shu Guogang ◽  
Chen Jun ◽  
Liu Yi ◽  
Liu Wei ◽  
...  
Keyword(s):  
Neutron Irradiation ◽  
Pressure Vessel ◽  
Power Plants ◽  
Hysteresis Loops ◽  
Reactor Pressure Vessel ◽  
Electromagnetic Properties ◽  
Irradiation Damage ◽  
Indentation Hardness ◽  
Rpv Steel ◽  
Reactor Pressure

The effect of neutron irradiation damage of reactor pressure vessel (RPV) steels is a main failure mode. Accelerated neutron irradiation experiments at 292 °C were conducted on RPV steels, followed by testing of the mechanical, electrical and magnetic properties for both the unirradiated and irradiated steels in a hot laboratory. The results showed that a significant increase in the strength, an obvious decrease in toughness, a corresponding increase in resistivity, and the clockwise turn of the hysteresis loops, resulting in a slight decrease in saturation magnetization when the RPV steel irradiation damage reached 0.0409 dpa; at the same time, the variation rate of the resistivity between the irradiated and unirradiated RPV steels shows good agreement with the variation rates of the mechanical properties parameters, such as nano-indentation hardness, ultimate tensile strength, yield strength at 0.2% offset, upper shelf energy and reference nil ductility transition temperature. Thus, as a complement to destructive mechanical testing, the resistivity variation can be used as a potentially non-destructive evaluation technique for the monitoring of the RPV steel irradiation damage of operational nuclear power plants.

Effect of Neutron Irradiation on the Mechanical Properties of an A508 CL2 and 15Kh2NMFA Irradiated in the NOMAD_3 Rig in the BR2 Cooling Water

2021 ◽  
Author(s):  
Inge Uytdenhouwen ◽  
Rachid Chaouadi
Keyword(s):  
Neutron Irradiation ◽  
Nuclear Reactor ◽  
Cooling Water ◽  
Charpy Impact ◽  
Tensile Tests ◽  
Significant Loss ◽  
Irradiation Temperature ◽  
Irradiation Damage ◽  
Transition Curves ◽  
Reactor Pressure

Abstract The typical operating temperatures of a nuclear reactor pressure vessel in a PWR are between 290°C and 300°C. However, many BWRs and some PWRs operate at slightly lower temperatures down to 260°C. Most of the literature and neutron irradiation damage is therefore focused on those irradiation temperatures. It is well-known that the lower the irradiation temperature, the more neutron irradiation damage occurs, because no appreciable annealing happens below approximately 230°C. The NOMAD_3 irradiation consisted in total of 24 Charpy sized samples from an A508 Cl.2 forging and a 15Kh2NMFA material. They were irradiated to three various fluences between 1.55 and 7.90 × 1019 n/cm2 (E > 1MeV) at approximately 100°C. The hardening of the A508 Cl.2 was between 260 and 400 MPa which was much higher than the NOMAD_0 properties which were irradiated at approximately 280°C. The tensile tests of irradiated materials are all characterized by a significant loss of work hardening capacity leading to plastic flow localization promptly after the yield strength is reached. This affects also the shape of the Charpy impact transition curves. The radiation embrittlement derived from Charpy impact tests, ΔT41J, is up to 156°C for the highest fluence. For this irradiation, the embrittlement to hardening ratio was also around 0.43 +/−0.2°C/MPa as it was found in the previous campaign NOMAD_0. This paper discusses the tensile, hardness and impact properties of the NOMAD_3 irradiation campaign. It is compared to the NOMAD_0 with respect to effect of irradiation temperature and annealing recovery.

Neutron irradiation damage in transition metal carbides

1991 ◽  
Vol 179-181 ◽  
pp. 461-464 ◽  
Author(s):  
Hisayuki Matsui ◽  
Kouji Nesaki ◽  
Michio Kiritani
Keyword(s):  
Transition Metal ◽  
Neutron Irradiation ◽  
Irradiation Damage ◽  
Metal Carbides ◽  
Transition Metal Carbides

The effect of neutron irradiation damage on the magnetic behavior of superconducting niobium in alternating fields

1974 ◽  
Vol 17 (3-4) ◽  
pp. 295-322 ◽  
Author(s):  
C. A. M. van der Klein ◽  
P. H. Kes ◽  
H. van Beelen ◽  
D. de Klerk
Keyword(s):  
Neutron Irradiation ◽  
Magnetic Behavior ◽  
Irradiation Damage

Neutron-Irradiation Damage in Stabilized ZrO2

1977 ◽  
Vol 60 (5-6) ◽  
pp. 287-288 ◽  
Author(s):  
F. W. CLINARD ◽  
D. L. ROHR ◽  
W. A. RANKEN
Keyword(s):  
Neutron Irradiation ◽  
Irradiation Damage

scholarly journals Neutron Irradiation Damage and Void Lattice Formation in a Molybdenum Alloy TZM

1993 ◽  
Vol 34 (11) ◽  
pp. 1137-1142 ◽  
Author(s):  
Katsunori Abe ◽  
Toru Masuyama ◽  
Manabu Satou ◽  
Margaret L. Hamilton
Keyword(s):  
Neutron Irradiation ◽  
Molybdenum Alloy ◽  
Irradiation Damage ◽  
Lattice Formation

scholarly journals The recovery of irradiation damage for Zircaloy-2 and Zircaloy-4 following low dose neutron irradiation at nominally 358 °C

2015 ◽  
Vol 461 ◽  
pp. 244-264 ◽  
Author(s):  
B.V. Cockeram ◽  
K.J. Leonard ◽  
T.S. Byun ◽  
L.L. Snead ◽  
J.L. Hollenbeck
Keyword(s):  
Neutron Irradiation ◽  
Low Dose ◽  
Irradiation Damage
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