Published 2005 | Version v1
Computer medium

The preliminary performance analysis of the metal fuel for the lead cooled critical transmutation reactor

  • 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)

Part of:
GLOBAL 2005: Proceedings of the international conference on nuclear energy systems for future generation and global sustainability

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)

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.