Thermal-stress analysis of HTGR fuel and control rod fuel blocks in in-block carbonization and annealing furnace
Description
The equivalent solid plate method, in conjunction with two-dimensional plane stress and plane strain analyses, was used in assessing the thermal stress behavior of HTGR fuel and control rod fuel blocks. For the control rod fuel blocks, particular attention was given to ascertaining the effects of the reserve shutdown hole and the control rod channel holes. The assumed safety factor of 2 on the failure criteria was considered adequate to account for neglecting the axial temperature gradient in the plane analyses of the ends of the blocks. The analyses indicated that the maximum calculated tensile stress values were smaller than the criteria values except for the plane strain analysis of the control rod fuel block end surfaces and the axisymmetric analysis of the fuel block as a circular cylinder. However, most of the maximum calculated strain values were greater than the criteria values
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A02/MF A01.
Files
Additional details
Publishing Information
- Imprint Pagination
- 12 p.
- Report number
- CONF-770807--28
Conference
- Title
- 4. international conference on structural mechanics in reactor technology.
- Dates
- 15 - 19 Aug 1977.
- Place
- San Francisco, California, United States of America (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 9358251
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ANNEALING; CONTROL ELEMENTS; FABRICATION; FUEL ELEMENTS; GRAPHITE; HTGR TYPE REACTORS; THERMAL STRESSES
- Descriptors DEC
- CARBON; ELEMENTS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HEAT TREATMENTS; NONMETALS; REACTOR COMPONENTS; REACTORS; STRESSES