Author: American Society of Mechanical Engineers. Materials and Fabrication Committee
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Performance and evaluation of light water reactor pressure vessels
Author: American Society of Mechanical Engineers. Materials and Fabrication Committee
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Performance and Evaluation of Light Water Reactor Pressure Vessels
Performance and Evaluation of Light Water Reactor Pressure Vessels
Author: R. Rungta
Publisher:
ISBN:
Category : Light water reactors
Languages : en
Pages : 128
Book Description
Publisher:
ISBN:
Category : Light water reactors
Languages : en
Pages : 128
Book Description
Performance and Evaluation of Light Water Reactor Pressure Vessels
High Performance Light Water Reactor
Author: Thomas Schulenberg
Publisher: KIT Scientific Publishing
ISBN: 3866448171
Category : Technology & Engineering
Languages : en
Pages : 258
Book Description
Results of the project "High Performance Light Water Reactor--Phase 2," carried out September 2006-February 2010 as part of the 6th European Framework Program.
Publisher: KIT Scientific Publishing
ISBN: 3866448171
Category : Technology & Engineering
Languages : en
Pages : 258
Book Description
Results of the project "High Performance Light Water Reactor--Phase 2," carried out September 2006-February 2010 as part of the 6th European Framework Program.
Probabilistic Study on the Rupture of Light Water Reactor Pressure Vessel
Author: J. Dufresne
Publisher:
ISBN:
Category : Light water reactors
Languages : en
Pages : 152
Book Description
Publisher:
ISBN:
Category : Light water reactors
Languages : en
Pages : 152
Book Description
Radiation Embrittlement and Surveillance of Nuclear Reactor Pressure Vessels: An International Study
Author: L. E. Steele
Publisher: ASTM International
ISBN:
Category :
Languages : en
Pages : 226
Book Description
Publisher: ASTM International
ISBN:
Category :
Languages : en
Pages : 226
Book Description
LWR Pressure Vessel Surveillance Dosimetry Improvement Program
Author:
Publisher:
ISBN:
Category : Light water reactors
Languages : en
Pages : 212
Book Description
Publisher:
ISBN:
Category : Light water reactors
Languages : en
Pages : 212
Book Description
Feasibility for Development of a Nuclear Reactor Pressure Vessel Flaw Distribution
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 14
Book Description
Pressurized water reactor pressure vessels operate under US Nuclear Regulatory Commission (NRC) rules and regulatory guides that are intended to maintain a low probability of vessel failure. The NRC has also addressed neutron embrittlement of pressurized water reactor pressure vessels by imposing regulations on plant operation. Plants failing to meet the operating criteria specified by these rules and regulations are required, among other things, to analytically demonstrate fitness for service in order to continue safe operation. The initial flaw size or distribution of initial vessel flaws is a key input to the required vessel integrity analyses. A fracture mechanics sensitivity study was performed to quantify the effect of the assumed flaw distribution on the predicted vessel performance under a specified pressurized thermal shock transient and to determine the critical crack size. Results of the analysis indicate that vessel performance in terms of the estimated probability of failure is very sensitive to the assumed flaw distribution. 20 refs., 3 figs., 2 tabs.
Publisher:
ISBN:
Category :
Languages : en
Pages : 14
Book Description
Pressurized water reactor pressure vessels operate under US Nuclear Regulatory Commission (NRC) rules and regulatory guides that are intended to maintain a low probability of vessel failure. The NRC has also addressed neutron embrittlement of pressurized water reactor pressure vessels by imposing regulations on plant operation. Plants failing to meet the operating criteria specified by these rules and regulations are required, among other things, to analytically demonstrate fitness for service in order to continue safe operation. The initial flaw size or distribution of initial vessel flaws is a key input to the required vessel integrity analyses. A fracture mechanics sensitivity study was performed to quantify the effect of the assumed flaw distribution on the predicted vessel performance under a specified pressurized thermal shock transient and to determine the critical crack size. Results of the analysis indicate that vessel performance in terms of the estimated probability of failure is very sensitive to the assumed flaw distribution. 20 refs., 3 figs., 2 tabs.
Light Water Reactor Pressure Isolation Valve Performance Testing
Author: H. H. Neely
Publisher:
ISBN:
Category : Light water reactors
Languages : en
Pages : 102
Book Description
Publisher:
ISBN:
Category : Light water reactors
Languages : en
Pages : 102
Book Description