The preliminary performance analysis of the metal fuel for the lead cooled critical transmutation reactor
Creators
- 1. Korea Atomic Energy Research Inst., Daejeon (Korea, Republic of)
Description
U-TRU-Zr metallic fuel is being considered as a transmutation fuel for a lead-cooled critical system in Korea. MACSIS-H for a metal fuel is being developed as a steady-state performance computer code. The fuel temperature distribution was analyzed by the MACSIS-H code. The constituent migration subroutine has been developed and installed into the MACSIS-H code to simulate the constituent redistribution. The He production rates calculated by the other code were inserted into the swelling/FGR routine of the code. The fission gas releases were predicted by the semi-theoretical models in MACSIS-H code. The thermal creep strain limits were analyzed according to the plenum-to-fuel ratio. The failure probabilities were estimated in terms of a CDF, based upon the Weibull statistical failure model. The preliminary study for developing the axial expansion model during the transient state conditions was introduced. (author)
Additional details
Publishing Information
- Publisher
- Atomic Energy Society of Japan
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- GLOBAL 2005: Proceedings of the international conference on nuclear energy systems for future generation and global sustainability
- Imprint Pagination
- [2562 p.]
- Journal Page Range
- [5 p.]
Conference
- Title
- International conference on nuclear energy systems for future generation and global sustainability
- Acronym
- GLOBAL 2005
- Dates
- 9-13 Oct 2005
- Place
- Tsukuba, Ibaraki (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 37056287
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; COOLING; FAILURES; FISSION PRODUCT RELEASE; LEAD; M CODES; METALS; NUCLEAR FUELS; NUMERICAL ANALYSIS; PERFORMANCE; REACTORS; STRAINS; SWELLING; THERMAL EXPANSION; TRANSMUTATION; TRANSURANIUM ELEMENTS; URANIUM; ZIRCONIUM
- Descriptors DEC
- ACTINIDES; COMPUTER CODES; DEFORMATION; ELEMENTS; ENERGY SOURCES; EXPANSION; FUELS; MATERIALS; MATHEMATICS; METALS; REACTOR MATERIALS; TRANSITION ELEMENTS
Optional Information
- Notes
- This CD-ROM can be used for WINDOWS 9x/NT/2000/ME/XP, MACINTOSH; Acrobat Reader is included; Data in PDF format, Folder Name GL0XX, Paper ID GL087DF.pdf; 13 refs., 7 figs., 1 tab.