Computational capability has been developed to calculate sensitivity coefficients of generalized responses with respect to cross-section data in the SCALE code system. The focus of this paper is the implementation of generalized perturbation theory (GPT) for one-dimensional and twodimensional deterministic neutron transport calculations. GPT is briefly summarized for computing sensitivity coefficients for reaction rate ratio responses within the existing framework of the TSUNAMI sensitivity and uncertainty (S/U) analysis code package in SCALE. GPT provides the capability to analyze generalized responses related to reactor analysis, such as homogenized cross-sections, relative powers, and conversion ratios, as well as measured experimental parameters such as 28 ρ (epithermal/thermal 238 U capture rates) in thermal benchmarks and fission ratios such as 239 Pu(n,f)/ 235 U(n,f) in fast benchmarks. The S/U analysis of these experimental integral responses can be used to augment the existing TSUNAMI S/U analysis capabilities for system similarity assessment and data adjustment. S/U analysis is provided for boiling water reactor pin cell as part of the Organization for Economic Cooperation and Development Uncertainty Analysis in Modeling benchmark.
[1]
Kostadin Ivanov,et al.
BENCHMARK FOR UNCERTAINTY ANALYSIS IN MODELING (UAM) FOR DESIGN, OPERATION AND SAFETY ANALYSIS OF LWRs
,
2007
.
[2]
G. C. Pomraning.
Variational Principle for Eigenvalue Equations
,
1967
.
[3]
W. M. Stacey,et al.
Variational Methods in Nuclear Reactor Physics
,
1975,
IEEE Transactions on Plasma Science.
[4]
Bradley T Rearden,et al.
SCALE-6 Sensitivity/Uncertainty Methods and Covariance Data
,
2008
.
[5]
J. Wallace Webster,et al.
Importance of The Adjoint Function
,
1968
.
[6]
A. Gandini,et al.
A generalized perturbation method for bi-linear functionals of the real and adjoint neutron fluxes
,
1967
.
[7]
L. N. Usachev.
Perturbation theory for the breeding ratio and for other number ratios pertaining to various reactor processes
,
1964
.