Published 1983 | Version v1
Book

Transient pellet-cladding interaction of LMFBR fuel rods - computer code ISUNE-5

Creators

  • 1. Iowa State Univ. of Science and Technology, Ames (USA). Dept. of Nuclear Engineering

Description

The transient fuel pellet-cladding interaction (PCI) of liquid-metal fast breeder reactor (LMFBR) fuel elements or rods is analyzed based on experimental results. The heat generation, ramp linear power rating, fuel restructuring, temperature distribution, bonding gap conductance, irradiation swelling, irradiation creep, fuel burnup, fission gas release, fuel pellet and cladding cracking, crack healing, radiation and oxidation corrosion, stress fatigue cracking, stress corrosion cracking, fuel performance, and reactor safety are taken into consideration. To improve the mixed (U, Pu)O2 or (U, Pu)C fuel performance and reactor safety, it is desired to: (a) increase the strength and ductility of structural material; (b) provide adequate gap distance and plenum space; (c) keep ramp-power increase rate slow, and (d) reduce the intensity and frequency of transient PCI in order to minimize SFC and SSC. (orig.)

Additional details

Publishing Information

Publisher
North-Holland.
Imprint Place
Amsterdam (Netherlands)
ISBN
0444 86693 0
Imprint Title
Transactions of the 7. international conference on structural mechanics in reactor technology. Vol. C
Imprint Pagination
313 p.
Journal Page Range
p. 147-154.

Conference

Title
7. international seminar on computational aspects of the finite element method (CAFEM-7) in conjunction with the 7. international conference on structural mechanics in reactor technology (SMIRT-7).
Dates
22-26 Aug 1983.
Place
Chicago, IL (USA).

INIS

Optional Information

Secondary number(s)
EUR--8596(Vol.C).