درباره ما
ASME STP-NU-013
IMPROVEMENT OF ASME NH FOR GRADE 91 NEGLIGIBLE CREEP AND CREEP FATIGUE
Organization:
ASME - ASME International
Year: 2008
Abstract: INTRODUCTION
In the frame of the AREVA HTR-VHTR design, it is recommended to operate the Reactor Pressure Vessel (RPV) in the negligible creep regime in order to avoid the implementation of a surveillance program covering the monitoring of the creep damage throughout the whole life of the reactor. Within the two options that are currently under consideration for the RPV material of ANTARES (AREVA New Technology based on Advanced gas cooled Reactor for Energy Supply), the high chromiumalloyed steel known as grade 91 in ASTM SA 336 standard has more creep properties documented and is also expected to allow more severe hot transients. The purpose of this report is to discuss the negligible creep conditions of this steel, also called Mod. 9Cr-1Mo. Mod. 9Cr-1Mo is a ferritic steel and not an austenitic stainless steel. Following ASME Boiler and Pressure Vessel (B&PV) Code, Section III for Class 1 nuclear components, additional rules of Subsection NH which take creep and creep/fatigue interaction effects into account should be used for applications above the limit of 371°C (700°F). Thus, the definition of the negligible creep conditions is of prime importance to enable the use of elevated core inlet temperatures during normal operating conditions (400°C at least) and to accommodate transients of limited duration. In addition, the negligible creep criteria will need to take account of the 60 year design life of the reactor which corresponds to 4.2×105 hours of operation (based on 80{}vailability).
In the frame of the AREVA HTR-VHTR design, it is recommended to operate the Reactor Pressure Vessel (RPV) in the negligible creep regime in order to avoid the implementation of a surveillance program covering the monitoring of the creep damage throughout the whole life of the reactor. Within the two options that are currently under consideration for the RPV material of ANTARES (AREVA New Technology based on Advanced gas cooled Reactor for Energy Supply), the high chromiumalloyed steel known as grade 91 in ASTM SA 336 standard has more creep properties documented and is also expected to allow more severe hot transients. The purpose of this report is to discuss the negligible creep conditions of this steel, also called Mod. 9Cr-1Mo. Mod. 9Cr-1Mo is a ferritic steel and not an austenitic stainless steel. Following ASME Boiler and Pressure Vessel (B&PV) Code, Section III for Class 1 nuclear components, additional rules of Subsection NH which take creep and creep/fatigue interaction effects into account should be used for applications above the limit of 371°C (700°F). Thus, the definition of the negligible creep conditions is of prime importance to enable the use of elevated core inlet temperatures during normal operating conditions (400°C at least) and to accommodate transients of limited duration. In addition, the negligible creep criteria will need to take account of the 60 year design life of the reactor which corresponds to 4.2×105 hours of operation (based on 80{}vailability).
Collections
:
-
Statistics
ASME STP-NU-013
Show full item record
| contributor author | ASME - ASME International | |
| date accessioned | 2017-09-04T16:35:23Z | |
| date available | 2017-09-04T16:35:23Z | |
| date copyright | 2008.09.03 | |
| date issued | 2008 | |
| identifier other | UZWSHFAAAAAAAAAA.pdf | |
| identifier uri | https://yse.yabesh.ir/std/handle/yse/98880 | |
| description abstract | INTRODUCTION In the frame of the AREVA HTR-VHTR design, it is recommended to operate the Reactor Pressure Vessel (RPV) in the negligible creep regime in order to avoid the implementation of a surveillance program covering the monitoring of the creep damage throughout the whole life of the reactor. Within the two options that are currently under consideration for the RPV material of ANTARES (AREVA New Technology based on Advanced gas cooled Reactor for Energy Supply), the high chromiumalloyed steel known as grade 91 in ASTM SA 336 standard has more creep properties documented and is also expected to allow more severe hot transients. The purpose of this report is to discuss the negligible creep conditions of this steel, also called Mod. 9Cr-1Mo. Mod. 9Cr-1Mo is a ferritic steel and not an austenitic stainless steel. Following ASME Boiler and Pressure Vessel (B&PV) Code, Section III for Class 1 nuclear components, additional rules of Subsection NH which take creep and creep/fatigue interaction effects into account should be used for applications above the limit of 371°C (700°F). Thus, the definition of the negligible creep conditions is of prime importance to enable the use of elevated core inlet temperatures during normal operating conditions (400°C at least) and to accommodate transients of limited duration. In addition, the negligible creep criteria will need to take account of the 60 year design life of the reactor which corresponds to 4.2×105 hours of operation (based on 80{}vailability). | |
| language | English | |
| title | ASME STP-NU-013 | num |
| title | IMPROVEMENT OF ASME NH FOR GRADE 91 NEGLIGIBLE CREEP AND CREEP FATIGUE | en |
| type | standard | |
| page | 147 | |
| status | Active | |
| tree | ASME - ASME International:;2008 | |
| contenttype | fulltext |