Fundamental principles for a nuclear design and structural analysis code for HTR components operating at temperatures above 8000C
Creators
- 1. Kernforschungsanlage Juelich G.m.b.H. (Germany, F.R.). Inst. fuer Reaktorwerkstoffe
Description
With reference to the special characteristics of an HTR plant for the supply of nuclear process heat, the investigation of the fundamental principles to form the basis for a high temperature nuclear structural design code has been described. As examples, preliminary design values are proposed for the creep rupture and fatigue behaviour. The linear damage accumulation rule is for practical reasons proposed for the determination of service life, and the difficulties in using this rule are discussed. Finally, using the data obtained in structural analysis, the main areas of investigation which will lead to improvements in the utilization of the materials are discussed. Based on the current information, the working group ''Design Code'' believes that a service life of 70000 h for the heat-exchanging components operating at above 8000C can be. (orig.)
Additional details
Publishing Information
- Journal Title
- Nucl. Eng. Des.
- Journal Volume
- 87
- Series
- Nucl. Eng. Des.
- Journal Page Range
- 345-355
- ISSN
- 0029-5493
- CODEN
- NEDEA
Conference
- Title
- 10. MPA seminar on the safety and reliability of pressure components with special emphasis on fracture exclusion.
- Dates
- 10-13 Oct 1984.
- Place
- Stuttgart (Germany, F.R.).
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 17040696
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; CREEP; HEAT EXCHANGERS; HIGH TEMPERATURE; HTGR TYPE REACTORS; LICENSING PROCEDURES; LIFETIME; PLANNING; PROCESS HEAT REACTORS; RUPTURES; THERMAL FATIGUE
- Descriptors DEC
- ADMINISTRATIVE PROCEDURES; FAILURES; FATIGUE; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; MECHANICAL PROPERTIES; POWER REACTORS; REACTORS; SIMULATION