RSICC CODE PACKAGE PSR-503
1. NAME AND TITLE
RODBURN/FEMAXI V: Code System for Calculating Power Distribution, Burn-up, and Thermal/Mechanical Properties of LWR Fuel Rods.
2. CONTRIBUTOR
Japanese Atomic Energy Research Institute,Tokai-mura, Nakagun, Japan through the NEA Data Bank, Issy-les-Moulineaux, France.
3. CODING LANGUAGE AND COMPUTER
FORTRAN 77; SUN and PC (P00503MNYCP00).
4. NATURE OF PROBLEM SOLVED
RODBURN calculates the power generation density profile in the radial and axial directions and fast neutron flux, and concentrations of fission product isotopes and fissile materials of a single rod irradiated in PWR, BWR and Halden BWR. RODBURN gives an output file which can be read by FEMAXI.
FEMAXI-V(ver.1) predicts the thermal and mechanical behavior of a light water reactor fuel rod during normal and transient (not accident) conditions. It can analyze the integral behavior of a whole fuel rod throughout its life as well as the localized behavior of a small part of fuel rod. Temperature distribution, radial and axial deformations, fission gas release, and inner gas pressure are calculated as a function of irradiation time and axial position. Stresses and strains in the pellet and cladding are calculated, and PCMI analysis is performed. Also, thermal conductivity degradation of pellet and cladding waterside oxidation are modeled. Its analytical capabilities also cover the boiling transient anticipated in BWR.
5. METHOD OF SOLUTION
RODBURN uses ORIGEN1 library, RABBLE library and other libraries. First, resonance integral is calculated. Then three group constants are selected, and simplified neutronics analysis is performed along the designated power history and rod geometries.
Elasto-plasticity creep, thermal expansion, pellet cracking and crack healing, relocation, densification, swelling, hot pressing, heat generation distribution, fission gas release, pellet-cladding mechanical interaction, cladding creep and oxidation are modeled by FEMAXI-V. Efforts have been made to improve numerical accuracy and stability of transient analysis.
6. RESTRICTIONS OR LIMITATIONS
None noted.
7. TYPICAL RUNNING TIME
RODBURN:Less than 1 minute in the sample case on SUN workstation.
FEMAXI V:Less than 10 minutes in the sample case on SUN workstation.
8. COMPUTER HARDWARE REQUIREMENTS
Sun and SUN compatible workstations and PC 486.
9. COMPUTER SOFTWARE REQUIREMENTS
UNIX: Solaris 2.5.1 and MS-DOS 6.0, Windows® 95, 98. A Fortran 77 compiler is required on Sun workstations. The Visual Fortran V5.0 compiler was used to create the PC executables included in the package.
10. REFERENCES
a) included in documentation in electronic format:
S. Motoe, Partial translation of input specifications from RODBURN manual.
S. Motoe, Partial translation of input specifications from FEMAXI-V manual.
b) background reference:
M. Suzuki and H. Saitou, "Light Water Reactor Fuel Analysis Code FEMAXI-V (Ver. 1), Detailed Structure and User's Manual," JAERI-Data/CODE 99-046 (1999) (in Japanese).
M. Uchida and H. Saito, "RODBURN: A Code for Calculating Power Distribution in Fuel Rods," JAERI-M 93-108 (1993) (in Japanese).
Included are the reference documents in (10.a) and the RODBURN/FEMAXI V source code in a 32-bit PKZIP from PKWARE® self-extracting executable. PC executables are included for IBM PC compatibles.
12. DATE OF ABSTRACT
November 2000.
KEYWORDS: BURNUP; REACTOR PHYSICS; LWR; STRESS ANALYSIS.