Zobrazeno 1 - 10
of 32
pro vyhledávání: '"B. Richard Bass"'
Autor:
Maksym Zarazovskii, Vladislav Pištora, Dana Lauerova, Florian Obermeier, Diego Fernando Mora Mendez, Yaroslav Dubyk, Tobias Bolinder, Carlos Cueto-Felgueroso Garcia, Szabolcs Szávai, Judit Dudra, Oriol Costa Garrido, Christophe Blain, Markku Puustinen, Jinya Katsuyama, B. Richard Bass, Paul T. Williams, Oleksii Shugailo
Publikováno v:
Volume 1: Codes and Standards.
The APAL (Advanced Pressurized Thermal Shock (PTS) Analysis for Long-Term Operation (LTO)) project was launched in October 2020 for four years with funding from the European Union’s HORIZON 2020 program. Within APAL, an extensive literature review
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ee12c9dcd32457d1a2a2956cc768d833
https://doi.org/10.1115/pvp2022-83699
https://doi.org/10.1115/pvp2022-83699
Publikováno v:
Volume 1B: Codes and Standards.
This paper presents an overview of added features in a new version of the FAVOR (Fracture Analysis of Vessels Oak Ridge) computer code called FAVOR-OCI. The original FAVOR code was developed at the US Department of Energy’s Oak Ridge National Labor
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ade6428e96c4d7cace4b4c504b2b31ec
https://doi.org/10.1115/pvp2018-84412
https://doi.org/10.1115/pvp2018-84412
Publikováno v:
Volume 6B: Materials and Fabrication.
This paper describes further results from an ongoing study of a simplified engineering model that is intended to account for effects of clad residual stresses on the propensity for initiation of preexisting inner-surface flaws in a commercial nuclear
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b2b88befea1e3a99d618fa69be2f4507
https://doi.org/10.1115/pvp2017-65255
https://doi.org/10.1115/pvp2017-65255
Autor:
Randy K. Nanstad, B. Richard Bass, Hilda B. Klasky, William Server, Paul T. Williams, Terry L. Dickson, Mikhail A. Sokolov, Sarma B Gorti
Publikováno v:
Volume 1A: Codes and Standards.
The Oak Ridge National Laboratory (ORNL) performed a detailed technical review of the 2015 Electrabel (EBL) Safety Cases prepared for the Belgium reactor pressure vessels (RPVs) at Doel 3 and Tihange 2 (D3/T2). The Federal Agency for Nuclear Control
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::88839c7285fa3114104108e41c46275a
https://doi.org/10.1115/pvp2017-65305
https://doi.org/10.1115/pvp2017-65305
Publikováno v:
Volume 1B: Codes and Standards.
This paper describes the development of a new computer code called Leak Analysis of Piping - Oak Ridge (LEAPOR) which calculates estimates for the leakage rate of water escaping from postulated through-wall cracks in a piping segment of a nuclear pow
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2c7db1cd9d2a2b1dfdc23625a7eb1875
https://doi.org/10.1115/pvp2017-65263
https://doi.org/10.1115/pvp2017-65263
Publikováno v:
Volume 1B: Codes and Standards.
This paper describes the current status of the Fracture Analysis of Vessels, Oak Ridge (FAVOR) computer code which has been under development at Oak Ridge National Laboratory (ORNL), with funding by the United States Nuclear Regulatory Commission (NR
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b76ab029abaeca2cc95be9bd0d53a988
https://doi.org/10.1115/pvp2017-65262
https://doi.org/10.1115/pvp2017-65262
Publikováno v:
Engineering Failure Analysis. 14:501-517
In recent years, probabilistic analyses have been playing an increasing role in safety assessments for nuclear power plants (NPPs) in the USA. An important example is the treatment of integrity analyses for the primary reactor pressure vessel (RPV) w
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c4fd8faeaa521a002d75434679d8dd00
https://doi.org/10.1016/j.engfailanal.2005.08.006
https://doi.org/10.1016/j.engfailanal.2005.08.006
Publikováno v:
Volume 6A: Materials and Fabrication.
Prior probabilistic fracture mechanics (PFM) analysis of reactor pressure vessels (RPVs) subjected to normal cool-down transients has shown that shallow, internal surface-breaking flaws dominate the RPV failure probability. This outcome is caused by
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::bfb3a92abe0a8725f674b6e25abb7dc1
https://doi.org/10.1115/pvp2015-45086
https://doi.org/10.1115/pvp2015-45086
Publikováno v:
Journal of Pressure Vessel Technology. 123:10-24
A technology to determine shallow-flaw fracture toughness of reactor pressure vessel (RPV) steels is being developed. This technology is for application to the safety assessment of RPVs containing postulated shallow-surface flaws. It has been shown t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c07113ca6ad07b686384e6b28e1acf97
https://doi.org/10.1115/1.1343910
https://doi.org/10.1115/1.1343910