scholarly journals Analysis of SORS: a computer program for analyzing fission product release from HTGR cores during transient temperature excursions

1978 ◽  
Author(s):  
J.M. Dickey
Keyword(s):  
Computer Program ◽  
Fission Product ◽  
Transient Temperature ◽  
Product Release

Implementation of A Gibbs Energy Minimizer In A Fission-Product Release Computer Program

2013 ◽  
Vol 2 (1) ◽  
pp. 39-48
Author(s):  
D.H. Barber
Keyword(s):  
Computer Program ◽  
Fission Product ◽  
Nuclear Physics ◽  
Noble Gas ◽  
Safety Margin ◽  
Fission Products ◽  
Nuclear Accidents ◽  
The Public ◽  
Product Release ◽  
Core Cooling

SOURCE 2.0 is the Canadian computer program for calculating fractional release of fission products from the UO2 fuel matrix. In nuclear accidents, fission-product release from fuel is one of the physical steps required before radiation dose from fission products can affect the public. Fission-product release calculations are a step in the analysis path to calculating dose consequences to the public from postulated nuclear accidents. SOURCE 2.0 contains a 1997 model of fission-product vaporization by B.J. Corse et al. based on lookup tables generated with the FACT computer program. That model was tractable on computers of that day. However, the understanding of fuel thermochemistry has advanced since that time. Additionally, computational resources have significantly improved since the time of the development of the Corse model and now allow incorporation of the more-rigorous thermodynamic treatment. Combining the newer Royal Military College of Canada (RMC) thermodynamic model of irradiated uranium dioxide fuel, a new model for fission-product vaporization from the fuel surface, a commercial user-callable thermodynamics subroutine library (ChemApp), an updated nuclide list, and updated nuclear physics data, a prototype computer program based on SOURCE IST 2.0P11 has been created that performs thermodynamic calculations internally. The resulting prototype code (with updated and revised data) provides estimates of 140La releases that are in better agreement with experiments than the original code version and data. The improvement can be quantified by a reduction in the mean difference between experimental and calculated release fractions from 0.70 to 0.07. 140La is taken to be representative of “low-volatile” fission products. To ensure that the existing acceptable performance for noble gases and volatile fission products is not adversely affected by the changes, comparisons were also made for a representative noble gas, 85Kr, and a representative volatile fission-product, 134Cs. These nuclides have the largest dataset in the SOURCE 2.0 validation test suite. This improvement provides increased confidence in the safety margin for equipment qualification in Loss-of-Coolant Accidents with Loss of Emergency Core Cooling.

Fission product release in high-burn-up UO2 oxidized to U3O8

2006 ◽  
Vol 348 (3) ◽  
pp. 229-242 ◽  
Author(s):  
J.Y. Colle ◽  
J.-P. Hiernaut ◽  
D. Papaioannou ◽  
C. Ronchi ◽  
A. Sasahara
Keyword(s):  
Fission Product ◽  
Product Release

A Three-Dimensional Finite Difference Solution for the Thermal Stresses in Railcar Wheels

1969 ◽  
Vol 91 (3) ◽  
pp. 891-896 ◽  
Author(s):  
G. E. Novak ◽  
B. J. Eck
Keyword(s):  
Computer Program ◽  
Thermal Stresses ◽  
Three Dimensional ◽  
Transient Temperature ◽  
Shear Stresses ◽  
Radial Temperature ◽  
Closed Form Solutions ◽  
Brake Application ◽  
History Of ◽  
Thin Disks

A numerical solution is presented for both the transient temperature and three-dimensional stress distribution in a railcar wheel resulting from a simulated emergency brake application. A computer program has been written for generating thermoelastic solutions applicable to wheels of arbitrary contour with temperature variations in both axial and radial directions. The results include the effect of shear stresses caused by the axial-radial temperature gradients and the high degree of boundary irregularity associated with this type of problem. The program has been validated by computing thermoelastic solutions for thin disks and long cylinders; the computed values being in good agreement with the closed form solutions. Currently, the computer program is being extended to general stress solutions corresponding to the transient temperature distributions obtained by simulated drag brake applications. When this work is completed, it will be possible to synthesize the thermal history of a railcar wheel and investigate the effects of wheel geometry in relation to thermal fatigue.

scholarly journals FISSION-PRODUCT-RELEASE MEASUREMENT FROM CLAD FUEL SPECIMENS

1962 ◽  
Author(s):  
M Kangilaski ◽  
A Bauer ◽  
F Rough ◽  
R Dickerson
Keyword(s):  
Fission Product ◽  
Product Release
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