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Journal Articles

Uncertainty-Accounted Calculational–Experimental Approach for Improved Conservative Evaluations of VVER RPV Radiation Loading Parameters

P. G. Borodkin, G. I. Borodkin, N. N. Khrennikov
Journal: Journal of ASTM International
Publisher: ASTM International
Article Type: Research-Article
J. ASTM Int.. April 2012, 9(4): 1–7.
https://doi.org/10.1520/JAI104019
Published Online: April 30, 2012
... calculations has been demonstrated in the paper. 20 05 2011 14 12 2011 01 04 2012 uncertainty calculation experiment VVER pressure vessel neutron fluence activity ex-vessel neutron dosimetry conservative approach References “ Recording of Fast Neutron Fluence at VVER...
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Journal Articles

Evaluation of Diamond Detectors for Fast Neutron Fluence Measurements in WWER-1000 Surveillance Assemblies

VA Nikolaenko, SM Zaritsky, IV Bachuchin
Journal: Journal of ASTM International
Publisher: ASTM International
Article Type: Research-Article
J. ASTM Int.. June 2006, 3(6): 1–8.
https://doi.org/10.1520/JAI13437
Published Online: June 1, 2006
...VA Nikolaenko; SM Zaritsky; IV Bachuchin The commonly used method of WWER-1000 surveillance dosimetry is based on the measurement of 54 Mn absolute activity in the material of surveillance specimens. Special procedures are necessary for the determination of the spectral index for each specimen...
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Journal Articles

Post-Irradiation Tensile Behavior and Residual Activity of Several Ferritic/Martensitic and Austenitic Steels Irradiated in Osiris Reactor at 325°C up to 9 dpa

Y de Carlan, X Averty, J-C Brachet, J-L Bertin, F Rozenblum, O Rabouille, A Bougault
Journal: Journal of ASTM International
Publisher: ASTM International
Article Type: Research-Article
J. ASTM Int.. September 2005, 2(8): 1–19.
https://doi.org/10.1520/JAI12354
Published Online: September 1, 2005
... suitable for use as irradiated components in a nuclear reactor [1]. The irradiated steels were austenitic stainless, martensitic (conventional and reduced activation), and ferritic-martensitic Oxide Dispersion Strengthened steels in various initial metallurgical conditions. The final dose was 9 dpa, which...
View Article titled, Post-Irradiation Tensile Behavior and Residual <span class="search-highlight">Activity</span> of Several Ferritic&#x2F;Martensitic and Austenitic Steels Irradiated in Osiris Reactor at 325°C up to 9 dpa
Open the PDF for Post-Irradiation Tensile Behavior and Residual <span class="search-highlight">Activity</span> of Several Ferritic/Martensitic and Austenitic Steels Irradiated in Osiris Reactor at 325°C up to 9 dpa in another window