CRP Publications
Type
Paper
Year
2018
Description
HONG, J-D., KIM, E., YANG, Y-S., KOOK, D-H., Mechanical Property Degradation of Unirradiated Zircaloy-4 Cladding After Creep Deformation, Nucl. Technol., 203 3 (2018) 282–292
Country/Organization
Rep. of Korea / KAERI
Type
Paper
Year
2018
Publication URL
https://vant.kipt.kharkov.ua/ARTICLE/VANT_2018_2/article_2018_2_63.pdf
Description
Efficiency of the dose rate calculation by monte-carlo method and point kernel method when handling radioactive waste / Rudychev, V.G., Azarenkov, N.A., Girka, I.O., Rudychev, Y.V. // Problems of Atomic Science and Technology (PAST). – 2018. – 2(114). P. 63-69.
Country/Organization
Ukraine / A.M. Pidgorny Institute for Mechanical Engineering Problems of the National Academy of Sciences of Ukraine
Type
Paper
Year
2019
Publication URL
http://www.inderscience.com/offer.php?id=106056
Description
Alyokhina S. Thermal state of ventilated storage container with spent nuclear fuel under normal operation. / International Journal of Nuclear Energy Science and Technology. No.4, Vol.13, 2019. – P4, Vol.13, 2019. – P. 381-398. – DOI: 10.1504/IJNEST.2019.106056.
Country/Organization
Ukraine / A.M. Pidgorny Institute for Mechanical Engineering Problems of the National Academy of Sciences of Ukraine
Type
Paper
Year
2018
Publication URL
http://www.ispnpp.kiev.ua/wp-content/uploads/2018/2018_30/c24.PDF
Description
Alekhina SV Thermal aspects of some emergencies during dry storage of spent nuclear fuel in ventilated containers // Problems of nuclear power plants and Chernobyl. - 2018.– Vip. 30. - P. 24-30 (in Ukranian)
Country/Organization
Ukraine / A.M. Pidgorny Institute for Mechanical Engineering Problems of the National Academy of Sciences of Ukraine
Type
Paper
Year
2018
Publication URL
https://journal-me.com/en/archive/vol21-2018-iss3-paper1/
Description
Alyokhina S. V. Problems of creating scientific and methodological bases of spent nuclear fuel dry cask storage thermal safety in Ukraine // Problems of mechanical engineering– 2018. – ?. 21, ???.3. – P. 4-12. DOI: 10.15407/pmach2018.03.004.
Country/Organization
Ukraine / A.M. Pidgorny Institute for Mechanical Engineering Problems of the National Academy of Sciences of Ukraine
Type
Paper
Year
2019
Description
RENGEL, M.A. MARTIN, RUIZ, J., “Ring compression testing of prehydrided PWR cladding with hydride blisters”, Proc. Global/Top Fuel 2019, American Nuclear Society, La Grange Park, IL (2019)
Country/Organization
Spain / Universidad Politécnica de Madrid (Enresa)
Type
Report
Year
2020
Description
ELECTRIC POWER RESEARCH INSTITUTE, High-Burnup Used Fuel Dry Storage System Thermal Modeling Benchmark: Round Robin Results, Rep. EPRI-3002013124, EPRI, Palo Alto, CA (2020).
Country/Organization
United States of America / EPRI
Type
Paper
Year
2020
Description
AKKURT, H., WONG, E., “Industrywide global efforts toward long term monitoring of neutron absorber materials in spent fuel pools”, Proc. Int. Conf. on Management of Spent Fuel from Nuclear Power Reactors 2019, IAEA, Vienna (2020).
Country/Organization
United States of America / EPRI
Type
Paper
Year
2019
Description
GONG, W., MILLE, M., ZUBLER, R., BERTSCH, J., Anisotropic influence of hydrides on Zircaloy fatigue, Proc. Global/Top Fuel 2019, American Nuclear Society, La Grange Park, IL (2019).
Country/Organization
Switzerland / PSI
Type
Report
Year
2019
Description
BRYAN, C.R., JAREK, R.L., FLORES, C., LEONARD, E., Analysis of Gas Samples Taken from the High Burnup Demonstration Cask, Rep. SAND2019-2281, Sandia Natl Lab, Albuquerque, NM (2019)
Country/Organization
United States of America / Sandia National Lab (EPRI)
Type
Report
Year
2017
Description
VLASSOPOULOS E., et al., Investigation of the properties and behaviour of spent nuclear fuel under conditions relevant for interim dry storage, handling and transportation: experimental setup optimisation and cold test campaign, NAGRA Arbeitsbericht NAB 16-67, March 2017
Country/Organization
Switzerland / NAGRA
Type
Paper
Year
2020
Publication URL
https://vant.kipt.kharkov.ua/ARTICLE/VANT_2020_2/article_2020_2_81.pdf
Description
S. Alyokhina, A. Kostikov, I. Koriahina Scientific Basis of Thermal Safety Analysis of Dry Storage of Spent Nuclear Fuel on Zaporizhska NPP // Problems of Atomic Science and Technology. 2020. ?2(126), p.81-84.
Country/Organization
Ukraine / A.M. Pidgorny Institute for Mechanical Engineering Problems of the National Academy of Sciences of Ukraine
Type
Paper
Year
2018
Publication URL
http://ee.zntu.edu.ua/article/view/143290/140843
Description
Alekhina SV Conditions of heat exchange in the container of dry storage of the spent nuclear fuel of power reactors // Electrical engineering and electric power. - 2018. - ?2. - P. 27-36. (in Ukrainian)
Country/Organization
Ukraine / A.M. Pidgorny Institute for Mechanical Engineering Problems of the National Academy of Sciences of Ukraine
Type
Paper
Year
2019
Description
AKKURT, H., QUIGLEY, A., HARRIS, M., "Accelerated Corrosion Tests to Evaluate the Long-Term Performance of BORAL® in Spent Fuel Pools”, Proc. 19th Int. Symp. Packaging and Transportation of Radioactive Materials, PATRAM 2019, August 4-9, 2019, New Orleans, LA, USA Curran Associates, Red Hook, NY (2019).
Country/Organization
United States of America / EPRI
Type
PhD Thesis
Description
Adrian Gomez, PhD thesis, in advance, Sabato Institute of Technology, San Martin University (UNSAM), Argentina
Country/Organization
Argentina / CNEA / San Martin University
Type
PhD Thesis
Description
Florencia Malamud, PhD thesis, Balseiro Institute, Cuyo University, Argentina
Country/Organization
Argentina / CNEA / Cuyo University
Type
Paper
Year
2019
Description
VIZCAINO, P., FLORES, A. V., VICENTE, M. A., SANTISTEBAN, J. R., DOMIZZI, G., TOLLEY, A., CONDÓ, A., ALMER, J., XIX ASTM International Symposium of the zirconium in the Nuclear Industry. Manchester, United Kingdom, May 20–23, 2019. Accepted for publication as a STP (Selected Technical Paper) of the Symposium.
Country/Organization
Argentina / CNEA
Type
Conference paper abstract
Year
2017
Description
Determination of the impact of solar radiation on the storage of spent nuclear fuel / S. Kapuza, S. Alekhina // XIII International Scientific and Technical Conference of Young Scientists and Specialists "Problems of Modern Nuclear Energy": Abstracts, October 18-20, 2017 p 40 (in Ukranian)
Country/Organization
Ukraine / A.M. Pidgorny Institute for Mechanical Engineering Problems of the National Academy of Sciences of Ukraine
Type
Paper
Year
2017
Description
RONDINELLA, V.V., NASYROW, R., PAPAIOANNOU, D. VLASSOPOULOS, E., CAPPIA, F., ET AL, “Mechanical integrity studies on spent nuclear fuel rods”, Proc. IHLRWMC 2017, Curran Associates, Red Hook, NY (2017) 734–740
Country/Organization
European Commission / JRC Karlsruhe
Type
Paper
Year
2017
Description
VLASSOPOULOS E., et al., "Destructive tests for determining mechanical integrity of spent nuclear fuel rods", Proc. 16th Int. High-Level Radioactive Waste Management Conf., April 9-13, 2017, Charlotte, NC, American Nuclear Society, La Grange Park, IL (2017).
Country/Organization
Switzerland / Nagra
Type
Paper
Year
2016
Description
MARTIN-RENGEL, M.A. RUIZ-HERVAIS, J., GOMEZ-SANCHEZ, F.J., RICO, A., RODRIGUEZ, J., “Determination of the Mechanical Properties of Blisters by Nanoindentation”, Top Fuel 2016 Proceedings, American Nuclear Society, La Grange Park, IL (2016)
Country/Organization
Spain / Universidad Politécnica de Madrid (Enresa)
Type
Paper
Year
2018
Publication URL
http://www.jnrd-nuclear.ro/images/JNRD/No.16/jnrd_168_art2.pdf
Description
Alyokhina S. Safety of the dry spent nuclear fuel storage. Thermal regimes / S.Alyokhina, D.Lunov // Journal of Nuclear Research and Development. – 2018. – ?. 3-7.
Country/Organization
Ukraine / A.M. Pidgorny Institute for Mechanical Engineering Problems of the National Academy of Sciences of Ukraine
Type
Paper
Year
2017
Publication URL
https://link.springer.com/article/10.1007/s10891-017-1686-7
Description
Identification of the Thermal Conductivity Coefficient for Quasi-Stationary Two-Dimensional Heat Conduction Equations / Yu. M. Matsevityi, S. V. Alekhina, V. T. Borukhov, G. M. Zayats, A. O. Kostikov // Journal of Engineering Physics and Thermophys-ics. – 2017. – V. 90, No.6. – ?. 1295-1310, DOI 10.1007/s10891-017-1686-7.
Country/Organization
Ukraine / A.M. Pidgorny Institute for Mechanical Engineering Problems of the National Academy of Sciences of Ukraine
Type
Paper
Year
2018
Publication URL
https://nuclear-journal.com/index.php/journal/article/view/119
Description
Alyokhina SV Determination of mutual thermal influence of containers with spent nuclear fuel on the open storage site / SV Alyokhina, AO Kostikov, DI Lunyov, OM Dybach, DO Dimitrieva // Nuclear and radiation safety. - 2018. - P. 49-53 (in Ukrainian)
Country/Organization
Ukraine / A.M. Pidgorny Institute for Mechanical Engineering Problems of the National Academy of Sciences of Ukraine
Type
Paper
Year
2017
Publication URL
http://npe.org.ua/wp-content/uploads/2019/02/10_2017.pdf
Description
Alekhina SV Thermal modes of storage of spent fuel assemblies in ventilated containers // Nuclear energy and environment. - 2017. - ? 2 (10). - P. 60-67. (in Ukranian)
Country/Organization
Ukraine / A.M. Pidgorny Institute for Mechanical Engineering Problems of the National Academy of Sciences of Ukraine
Type
Paper
Year
2017
Publication URL
https://www.sciencedirect.com/science/article/pii/S1738573317301250
Description
Alyokhina S. Unsteady heat exchange at the dry spent nuclear fuel storage / S.Alyokhina, A.Kostikov // Nuclear Engineering and Technology. – 2017. – V.49, Iss.7, Oct. – P. 1457-1462
Country/Organization
Ukraine / A.M. Pidgorny Institute for Mechanical Engineering Problems of the National Academy of Sciences of Ukraine
Type
Report
Year
2018
Description
ELECTRIC POWER RESEARCH INSTITUTE, Evaluation of the Impact of Neutron Absorber Material Blistering and Pitting on Spent Fuel Pool Reactivity, Rep. EPRI-3002013119, EPRI, Palo Alto, CA (2018).
Country/Organization
United States of America / EPRI
Type
PhD reference
Year
2019
Description
Alekhina SV Scientific bases of thermal safety of dry storage of spent nuclear fuel: author's ref. dis. for science. degree of doctor of technical sciences Science: special. 05.14.14 "Thermal and nuclear power plants" / SV Alekhina. - Odessa, 2019. - 38 p. (in Ukranian)
Country/Organization
Ukraine / A.M. Pidgorny Institute for Mechanical Engineering Problems of the National Academy of Sciences of Ukraine
Type
Conference Paper
Year
2017
Description
Alekhina S.V., Kruglov S.A. Analysis of the injected into the heat on heat-cut containers of dry recovery from the nuclear firing. - "Innovative ways of modernization of basic industries, energy and resource conservation, environmental protection", VI International scientific and practical conference of young scientists and specialists in the field of designing enterprises of the mining and metallurgical complex, energy and resource conservation and environmental protection , 22-23 March 2017 p119-123 (in Russian)
Country/Organization
Ukraine / A.M. Pidgorny Institute for Mechanical Engineering Problems of the National Academy of Sciences of Ukraine
Type
Paper
Year
2016
Description
NASYROW R., et al., Bending Test Device for Mechanical Integrity Studies of Spent Nuclear Fuel Rods, Proceedings of PATRAM 2016 Kobe (Japan), Institute of Nuclear Materials Management, Mount Laurel, NJ (2016).
Country/Organization
European Commission / JRC Karlsruhe
Type
Paper
Year
2017
Description
WALTERS, W.S., DURHAM, P., HODGE, N., The adsorption of water from a carbonaceous deposit layer on the surface of stainless steel representing spent AGR nuclear fuel cladding, J. Nucl. Sci. Technol. 55 (2017) 374–385
Country/Organization
United Kingdom / NNL
Type
Paper
Year
2017
Description
VLASSOPOULULOS E., et al., Mechanical Integrity of Used Nuclear Fuel: From Experimental to Numerical Studies, Proc. 2018 Reactor Fuel Performance Meeting TopFuel 2018, European Nuclear Society, Brussels, Belgium (2018).
Country/Organization
Switzerland / NAGRA
Type
Presentation
Year
2019
Description
HONG, J-D., KIM, E., KIM, S. G., YANG, Y-S., KOOK, D-H, Zircaloy-4 cladding degradation tests under simulated dry storage conditions - creep and delayed hydride cracking, Pres. Intl High-Level Radioactive Waste Management Meeting 2019, April 14-18, 2019, Knoxville Convention Center, Knoxville, TN
Country/Organization
Rep. of Korea / KAERI
Type
PhD Thesis
Description
Lucia Buitrago, PhD thesis, Balseiro Institute, Cuyo University, Argentina
Country/Organization
Argentina / CNEA / Cuyo University
Type
Paper
Year
2019
Publication URL
https://vant.kipt.kharkov.ua/ARTICLE/VANT_2019_5/article_2019_5_75.pdf
Description
Alyokhina S., Matsevity Y., Dudkin V., Poskas R., Sirvydas A., Rackaitis K., Zujus R. Comparative analysis of numerical methods used for thermal modeling of spent nuclear fuel dry storage systems // Problems of Atomic Science and Technology. Iss. 5, 2019, P. 75-79.
Country/Organization
Ukraine / A.M. Pidgorny Institute for Mechanical Engineering Problems of the National Academy of Sciences of Ukraine
Type
PhD Thesis
Description
Alvaro Moya Riffo, PhD thesis, Balseiro Institute, Cuyo University, Argentina
Country/Organization
Argentina / CNEA / Cuyo University
Type
Conference presentation
Year
2019
Description
COLLDEWEIH, A.W., GONG, W., ZUBLER, R., BERTSCH, J., TRTIK, P., Influence of cracking direction during DHC of zircaloy-2 cladding, Presented at TopFuel 2019, 22–27 September 2019, Seattle
Country/Organization
Switzerland / PSI
Type
Paper
Year
2019
Description
AKKURT, H., “Overview of EPRI Research on Evaluation of Long Term Performance of Neutron Absorber Material Performance in Spent Fuel Pools” Proc. 17th International High-Level Radioactive Waste Management Conference, Curran Associates Red Hook, NY (2019).
Country/Organization
United States of America / EPRI
Type
Paper
Year
2018
Publication URL
https://vant.kipt.kharkov.ua/ARTICLE/VANT_2018_2/article_2018_2_57.pdf
Description
Alyokhina S. Solar Radiation Influence On The Spent Nuclear Fuel Dry Storage Container / S.Alyokhina, S.Kapuza, A.Kostikov // Problems Of Atomic Science And Technology (PAST). – 2018. – 2(114). P.57-62.
Country/Organization
Ukraine / A.M. Pidgorny Institute for Mechanical Engineering Problems of the National Academy of Sciences of Ukraine
Type
Report
Year
2018
Description
ELECTRIC POWER RESEARCH INSTITUTE, Roadmap for the Industrywide Learning Aging Management Program (i-LAMP): For Neutron Absorber Materials in Spent Fuel Pools, Rep. EPRI-3002013122 EPRI, Palo Alto, CA (2018).
Country/Organization
United States of America / EPRI
Type
Paper
Year
2019
Publication URL
https://www.osti.gov/pages/servlets/purl/1569845
Description
VICENTE ALVAREZ, M. A., SANTISTEBAN, J. R., DOMIZZI, G., OKASINSKI, J., ALMER, J., Elastic strain tensor of zirconium hydrides in Zr2.5%Nb pressure tubes by synchrotron X-ray diffraction, J. Appl. Cryst. 52 (2019) 1128–1143
Country/Organization
Argentina / CNEA
Type
PhD Thesis
Year
2019
Description
Thesis of the Doctor of Sciences "Scientific Bases of the Thermal Safety of the Spent Nuclear Fuel Dry Storage" by Svitlana Alyokhina, 30 May 2019
Country/Organization
Ukraine / A.M. Pidgorny Institute for Mechanical Engineering Problems of the National Academy of Sciences of Ukraine
Type
Paper
Year
2018
Publication URL
https://nuclear-journal.com/index.php/journal/article/view/98
Description
Alekhina SV Forecasting of temperatures in a container with spent nuclear fuel / SV Alyokhina, OM Dybach, AO Kostikov, DO Dimitrieva // Nuclear and radiation safety. - 2018. - ?2 (78). - P. 31-35 (in Ukrainian)
Country/Organization
Ukraine / A.M. Pidgorny Institute for Mechanical Engineering Problems of the National Academy of Sciences of Ukraine
Type
Paper
Year
2018
Description
GONG, W., TRTIK, P., VALANCE, S., BERTSCH, J., Hydrogen diffusion under stress in zircaloy: High resolution neutron radiography and finite element modelling, J. Nucl. Mat. 508 (2018) 459–464.
Country/Organization
Switzerland / PSI
Type
Paper
Year
2017
Publication URL
https://vant.kipt.kharkov.ua/ARTICLE/VANT_2017_2/article_2017_2_91.pdf
Description
Rudychev V.G., Azarenkov M.O., Girka I.O., Rudychev Y.V., Shchus O.P. Contribution of Radionuclides to Heat Release In the Process of SNF Dry Storage // Problems of Atomic Science And Technology (PAST). – 2017. – 2(108). P. 91-96.
Country/Organization
Ukraine / A.M. Pidgorny Institute for Mechanical Engineering Problems of the National Academy of Sciences of Ukraine
Type
PhD Thesis
Description
Constanza Buioli, PhD thesis, in advance, Sabato Institute of Technology, San Martin University (UNSAM), Argentina
Country/Organization
Argentina / CNEA / San Martin University
Type
Presentation
Year
2016
Description
FERNÁNDEZ, F.J., et al, “Dry cask monitoring at José Cabrera NPP”, Presented at EPRI ESCP Winter Meeting, November 2016, Charlotte, NC
Country/Organization
Spain / Enresa
Type
Master's Thesis
Year
2019
Description
Diana Kubova,"Analysis of weld joints of ATABOR steels", Faculty of Materials Science and Technology, Trnava, 2019
Country/Organization
Slovakia / VUJE
Type
Paper
Year
2018
Publication URL
https://www.sciencedirect.com/science/article/pii/S173857331730699X?via%3Dihub
Description
Alyokhina S. Thermal Analysis of Certain Accident Conditions of the Dry Spent Nuclear Fuel Storage // Nuclear Engineering and Technology. – 2018. – V. 50, Iss. 5. – P.717-723, DOI: 10.1016/j.net.2018.03.002.
Country/Organization
Ukraine / A.M. Pidgorny Institute for Mechanical Engineering Problems of the National Academy of Sciences of Ukraine
Type
Paper
Year
2017
Description
GONG, W., TRTIK, P., ZUBLER, R., BERTSCH, J., Stress induced hydrogen redistribution in zircaloy measured by high resolution neutron imaging, Presented at 2017 Water reactor fuel performance meeting, 10–14 September 2017, Jeju.
Country/Organization
Switzerland / PSI
Type
Paper
Year
2016
Publication URL
https://www.sciencedirect.com/science/article/abs/pii/S135964541630489X
Description
VICENTE ALVAREZ, M.A., SANTISTEBAN, J.R., VIZCAÍNO, P., RIBARIK, G., UNGAR, T., Quantification of dislocations densities in zirconium hydride by X-ray line profile analysis, J. Acta Mat. 117 (2016) 1–12
Country/Organization
Argentina / CNEA
Type
Paper
Year
2017
Publication URL
https://vant.kipt.kharkov.ua/ARTICLE/VANT_2017_2/article_2017_2_70.pdf
Description
Alyokhina S. Safety Issues Of The Dry Storage Of The Spent Nuclear Fuel / S. Alyokhina, A. Kostikov, S.Kruhlov // Problems Of Atomic Science And Technology (PAST). – 2017. – 2(108). P. 70-74.
Country/Organization
Ukraine / A.M. Pidgorny Institute for Mechanical Engineering Problems of the National Academy of Sciences of Ukraine
