A Method to Estimate Fission Product Concentration Uncertainty in a Multi-Time-Step MCNP6 Code Nuclear Fuel Burnup Calculation

2019 ◽  
Vol 206 (1) ◽  
pp. 73-81
Author(s):  
Yasuhiro Minamigawa ◽  
Evans D. Kitcher ◽  
Sunil S. Chirayath
Keyword(s):  
Fission Product ◽  
Nuclear Fuel ◽  
Fuel Burnup ◽  
Product Concentration ◽  
Time Step ◽  
Burnup Calculation

Determination of Nuclear Fuel Burnup from Fission Product Analysis

1970 ◽  
Vol 42 (2) ◽  
pp. 215-219 ◽  
Author(s):  
F. L. Lisman ◽  
W. J. Maeck ◽  
J. E. Rein
Keyword(s):  
Fission Product ◽  
Nuclear Fuel ◽  
Fuel Burnup ◽  
Product Analysis ◽  
Fission Product Analysis

scholarly journals Evaluation of fission product worth margins in PWR spent nuclear fuel burnup credit calculations.

10.2172/12014 ◽  
1999 ◽  
Author(s):  
R.N. Blomquist ◽  
P.J. Finck ◽  
C. Jammes ◽  
C.G. Stenberg
Keyword(s):  
Fission Product ◽  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Fuel Burnup

Reactor Fuel Burnup Calculation for a Square Lattice Cell

1981 ◽  
Vol 77 (2) ◽  
pp. 235-250 ◽  
Author(s):  
Y. Y. Chang ◽  
S. K. Loyalka
Keyword(s):  
Reactor Fuel ◽  
Fuel Burnup ◽  
Square Lattice ◽  
Lattice Cell ◽  
Burnup Calculation

METHODS FOR EVALUATING THE ACCURACY OF FISSION PRODUCT CONCENTRATION MEASUREMENTS IN NUCLEAR REACTOR PRIMARY HEAT TRANSPORT SYSTEMS

2014 ◽  
Vol 3 (01) ◽  
pp. 29-36 ◽  
Author(s):  
Steve Livingstone
Keyword(s):  
Fission Product ◽  
Heat Transport ◽  
Nuclear Reactor ◽  
A Priori ◽  
Reactor Core ◽  
Transport Systems ◽  
Product Concentration ◽  
Concentration Measurements ◽  
Reactor Types ◽  
Commercial Applications

Fission product concentration in reactor primary heat transport systems is a common diagnostic indicator for assessing reactor core condition and determining the presence, size, power, location, residence time, burnup, etc., of defected fuel. Typically, diagnostic assessment assumes a priori that measured data (activity concentration measurements and reactor parameters) are accurate; however, this is not always a valid assumption. A set of novel methods has been developed for detecting minor discrepancies in fission product concentration measurements and reactor parameters (such as issues with transit times, purification, and spectral analysis). A variety of techniques are discussed and applied to a variety of reactor types (mainly commercial power plant designs); these techniques and concepts can be modified and applied for research and (or) commercial applications.

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