Zobrazeno 1 - 10
of 36
pro vyhledávání: '"Terry L. Dickson"'
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
Publikováno v:
Volume 1B: Codes and Standards.
A probabilistic fracture mechanics (PFM) analysis code PASCAL has been developed by Japan Atomic Energy Agency based on Japanese methods and data to evaluate failure probabilities and failure frequencies of Japanese reactor pressure vessels (RPVs) co
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
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
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
Publikováno v:
Volume 1B: Codes and Standards.
A probabilistic fracture mechanics (PFM) analysis code called PASCAL has been developed by the Japan Atomic Energy Agency to evaluate failure frequencies of Japanese reactor pressure vessels (RPVs) during pressurized thermal shock (PTS) events based
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
Autor:
Bennett Richard Bass, Hilda B. Klasky, Sarma B Gorti, William Server, Paul T. Williams, Terry L. Dickson, Randy K. Nanstad, Mikhail A. Sokolov
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::094108d660ec4cc7e15472f8b8dd37b0
https://doi.org/10.2172/1234350
https://doi.org/10.2172/1234350
Autor:
Cristian Rabiti, William Hoffman, Richard Bass, Benjamin Spencer, Sonat Sen, Terry L. Dickson
The Grizzly code is being developed with the goal of creating a general tool that can be applied to study a variety of degradation mechanisms in nuclear power plant components. The first application of Grizzly has been to study fracture in embrittled
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::970f0c5f16299475cb3338abb4394856
https://doi.org/10.2172/1244643
https://doi.org/10.2172/1244643