Published October 2017
| Version v1
Miscellaneous
Thermal conductivity modeling of U-TRU-RE-Zr metal fuel for PGSFR
Creators
- 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
Description
In is paper, the thermal conductivity model of UTRU-RE-Zr was developed based on the theory of two phase solid bodies using the existing thermal conductivity model of U-Pu-Zr alloy, the available data in the literature and the thermal conductivity theories of the solid solution. The thermal conductivity model of U-TRU-RE-Zr for PGSFR was developed and compared with the measured data. Even though more experimental data are needed, the developed models have a good capability to calculate the thermal conductivity. This work forms the basis for the establishment of key technology that will evaluate the performance of UTRU-RE-Zr metal fuel
Additional details
Publishing Information
- Publisher
- KRS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Title
- Proceedings of the Conference and Symposium Korean Radioactive Waste Society Fall Meeting 2017
- Imprint Pagination
- 384 p.
- Journal Page Range
- p. 93-94
Conference
- Title
- 2017 Fall Meeting of Korean Radioactive Waste Society
- Dates
- 18 Oct 2017
- Place
- Daejeon (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 49096234
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- AVAILABILITY; PERFORMANCE; SIMULATION; SODIUM COOLED REACTORS; THERMAL CONDUCTIVITY; URANIUM ALLOYS
- Descriptors DEC
- ACTINIDE ALLOYS; ALLOYS; LIQUID METAL COOLED REACTORS; PHYSICAL PROPERTIES; REACTORS; THERMODYNAMIC PROPERTIES
Optional Information
- Notes
- 5 refs, 3 figs