The Experts below are selected from a list of 318 Experts worldwide ranked by ideXlab platform
Chen Guan-hu - One of the best experts on this subject based on the ideXlab platform.
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Dynamic characteristics analysis of half-through concrete filled steel tublar arch bridge
2007Co-Authors: Chen Guan-huAbstract:The half-through concrete filled steel tublar arch bridge's three-dimensional finite element model is established and the natural frequency and modes are calculated through the application of the finite element analysis software.The calculating results can offer the related technical parameters and basic data for the Design Certification,construction,health detection and maintenance in working conditions.
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Spatial stability analysis of half-through concrete filled steel tublar arch bridge
2007Co-Authors: Chen Guan-huAbstract:The half-through concrete filled steel tublar arch bridge's three-dimensional finite element model is established and the stability coefficient of safety and modes are calculated through the application of the finite element analysis software.The calculating results can offer the related technical parameters and basic data for the Design Certification,construction,health detection and maintenance in working conditions.
S.w. Sorrell - One of the best experts on this subject based on the ideXlab platform.
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Application of the risk oriented accident analysis methodology (ROAAM) to severe accident management in the AP600 advanced light water reactor
Reliability Engineering & System Safety, 1998Co-Authors: J.h. Scobel, T.g. Theofanous, S.w. SorrellAbstract:Abstract An important part of the AP600 Design, as well as of the Design Certification review by the US Nuclear Regulatory Commission, is devoted to ensuring defense in depth through deep consideration and management of severe accidents. Going beyond the traditional Level 2 PRA, in this article we show how this defense in depth was achieved and demonstrated in a consistent manner between prevention and mitigation, through application of the Integrated ROAAM approach. This requires the up-front integration of probabilistic and deterministic thought, which leads naturally to clear and coherent safety goals as an overall guide toward closure.
C.b. Brinkman - One of the best experts on this subject based on the ideXlab platform.
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Regulatory issues resolved through Design Certification on the System 80+{trademark} standard plant Design
1996Co-Authors: S.e. Ritterbusch, C.b. BrinkmanAbstract:The US Nuclear Regulatory Commission (NRC) has completed its review of the System 80+{trademark} Standard Plant Design, approving advanced Design features and closing severe accident licensing issues. Final Design Approval was granted in July 1994. The NRC review was extensive, requiring written responses to over 4,950 questions and formal printing of over 50,000 Safety Analysis Report pages. New safety issues never before addressed in a regulatory atmosphere had to be resolved with detailed analysis and evaluation of Design features. the System 80+ review demonstrated that regulatory issues can be firmly resolved only through presentation of a detailed Design and completion of a comprehensive regulatory review.
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System 80+ standard plant-licensing experience
Transactions of the American Nuclear Society, 1995Co-Authors: C.b. BrinkmanAbstract:ABB Combustion Engineering has successfully obtained a final Design approval for its advanced light water reactor (ALWR), System 80+ standard plant, and is well into the process of codifying the Design through the rulemaking Certification process under 10CFR52. When this exercise is completed in 1996, System 80+ will become the first advanced pressurized water reactor Design to have a Design Certification rule available for referencing in Part 52 combined license applications or Part 50 construction permit or operating license applications. The Design Certification rule provides U.S. Nuclear Regulatory Commission (NRC) preapproval and licensing finality of the System 80+ Design for all combined license or operating license applications referencing it.
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Lessons learned from Design Certification of system 80
1994Co-Authors: Ga Davis, R.a. Matzie, C.b. Brinkman, RitterbuschAbstract:ABB Combustion Engineering began the development of the System 80+ standardized nuclear plant Design in 1986. System 80+ is a 1350 MWe evolutionary, Advanced Light Water Reactor (ALWR) nuclear plant employing a pressurized water reactor. As the Design information was produced, it was submitted to the U.S. Nuclear Regulatory Commission (NRQ for approval under the NRCs new licensing regulations for standardized Designs, 10CFR52. The new NRC regulations require that standard Designs for future nuclear plants must address safety issues that were not specifically required for the current generation of nuclear plants operating in the United States. The new requirements are grouped into three categories: (1) performance of a Probabilistic Risk Assessment (PRA) and consideration of Design improvements based upon insights from the PRA, (2) resolution of the NRCs unresolved and generic safety issues, and (3) consideration of severe accidents (involving core melt) in the Design of the plant The new NRC requirements, combined with feedback from utilities via the EPRI ALWR Utility Requirements Document (URD), resulted in substantial changes to ABB-CE's earlier standard Design, System 80, which is currently operating in the United States at the Palo Verde site and is under construction at two sites in the Republic of Korea. The new standard Design, System 80+, has essentially completed NRC review. A Final Design Approval (FDA) is scheduled by the NRC in August 1994.
R.a. Matzie - One of the best experts on this subject based on the ideXlab platform.
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Lessons learned from Design Certification of system 80
1994Co-Authors: Ga Davis, R.a. Matzie, C.b. Brinkman, RitterbuschAbstract:ABB Combustion Engineering began the development of the System 80+ standardized nuclear plant Design in 1986. System 80+ is a 1350 MWe evolutionary, Advanced Light Water Reactor (ALWR) nuclear plant employing a pressurized water reactor. As the Design information was produced, it was submitted to the U.S. Nuclear Regulatory Commission (NRQ for approval under the NRCs new licensing regulations for standardized Designs, 10CFR52. The new NRC regulations require that standard Designs for future nuclear plants must address safety issues that were not specifically required for the current generation of nuclear plants operating in the United States. The new requirements are grouped into three categories: (1) performance of a Probabilistic Risk Assessment (PRA) and consideration of Design improvements based upon insights from the PRA, (2) resolution of the NRCs unresolved and generic safety issues, and (3) consideration of severe accidents (involving core melt) in the Design of the plant The new NRC requirements, combined with feedback from utilities via the EPRI ALWR Utility Requirements Document (URD), resulted in substantial changes to ABB-CE's earlier standard Design, System 80, which is currently operating in the United States at the Palo Verde site and is under construction at two sites in the Republic of Korea. The new standard Design, System 80+, has essentially completed NRC review. A Final Design Approval (FDA) is scheduled by the NRC in August 1994.
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Status of system 80+ Design Certification
1992Co-Authors: R.a. MatzieAbstract:This paper reports that 1991 was a year of great progress in the Design Certification process for ABB Combustion Engineering Nuclear Power's 1300 MWe evolutionary advanced light water reactor (ALWR) plant, System 80+. As the next generation of nuclear power plants move toward final Design approval by the U.S. Nuclear Regulatory Commission (NRC), elements of the Design process that emphasize operation and maintenance have become the focus. For System 80+, licensing under the new Design Certification process is now concentrated on operational support, human engineering, plant layout, and computer-aided engineering.
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The status of System 80+ development and licensing
Transactions of the American Nuclear Society, 1992Co-Authors: R.e. Newman, R.a. MatzieAbstract:ABB-Combustion Engineering Nuclear Power (ABB-CENP) has been concentrating on the development of its large evolutionary advanced light water reactor (ALWR) System 80+ over the past 5 yr. The System 80+ standard plant Design is an advanced version of the three reactors currently in operation at Palo Verde, Arizona, and the four reactors under construction at Yonggwang and Ulchin in the Republic of Korea. It incorporates the advanced features recommended by the US utility industry as specified in the ALWR Utility Requirements Document and addresses new US Nuclear Regulatory Commission (NRC) licensing requirements aimed at mitigating the consequences of severe accidents. System 80+ will be the first advanced and pressurized water reactor to receive final Design approval and Design Certification under the new regulatory process, 10CFR52.
J.h. Scobel - One of the best experts on this subject based on the ideXlab platform.
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Application of the risk oriented accident analysis methodology (ROAAM) to severe accident management in the AP600 advanced light water reactor
Reliability Engineering & System Safety, 1998Co-Authors: J.h. Scobel, T.g. Theofanous, S.w. SorrellAbstract:Abstract An important part of the AP600 Design, as well as of the Design Certification review by the US Nuclear Regulatory Commission, is devoted to ensuring defense in depth through deep consideration and management of severe accidents. Going beyond the traditional Level 2 PRA, in this article we show how this defense in depth was achieved and demonstrated in a consistent manner between prevention and mitigation, through application of the Integrated ROAAM approach. This requires the up-front integration of probabilistic and deterministic thought, which leads naturally to clear and coherent safety goals as an overall guide toward closure.