SENSMG: First-Order Sensitivities of Neutron Reaction Rates, Reaction-Rate Ratios, Leakage, k eff, and α Using PARTISN
Abstract
SENSMG is a tool for computing first-order sensitivities of neutron reaction rates, reaction-rate ratios, leakage, k eff, and α using the PARTISN multigroup discrete-ordinates code. SENSMG computes sensitivities to all of the transport cross sections and data (total, fission, nu, chi, and all scattering moments), two edit cross sections (absorption and capture), and the density for every isotope and energy group. It also computes sensitivities to the mass density for every material and derivatives with respect to all interface locations. The tool can be used for one-dimensional spherical (r) and two-dimensional cylindrical (r-z) geometries. The tool can be used for fixed-source and eigenvalue problems. The tool implements Generalized Perturbation Theory (GPT) as discussed by Williams and Stacey. Section II of this report describes the theory behind adjoint-based sensitivities, gives the equations that SENSMG solves, and defines the sensitivities that are output. Section III describes the user interface, including the input file and command line options. Section IV describes the output. Section V gives some notes about the coding that may be of interest. Section VI discusses verification, which is ongoing. Section VII lists needs and ideas for future work. Appendix A lists all of the input files whose results aremore »
- Authors:
-
- Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
- Publication Date:
- Research Org.:
- Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
- Sponsoring Org.:
- USDOE National Nuclear Security Administration (NNSA)
- OSTI Identifier:
- 1333129
- Report Number(s):
- LA-UR-16-28943
TRN: US1700750
- DOE Contract Number:
- AC52-06NA25396
- Resource Type:
- Technical Report
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 73 NUCLEAR PHYSICS AND RADIATION PHYSICS; NEUTRON REACTIONS; NUCLEAR REACTION KINETICS; SENSITIVITY; DENSITY; DISCRETE ORDINATE METHOD; EIGENVALUES; NEUTRON LEAKAGE; CROSS SECTIONS; CYLINDRICAL CONFIGURATION; PERTURBATION THEORY; SPHERICAL CONFIGURATION; ABSORPTION; FISSION; INTERFACES; ONE-DIMENSIONAL CALCULATIONS; TWO-DIMENSIONAL CALCULATIONS; CAPTURE; EQUATIONS; MASS; SCATTERING; NEUTRON TRANSPORT; VERIFICATION; S CODES; MULTIPLICATION FACTORS; MULTIGROUP THEORY; TOTAL CROSS SECTIONS; ADJOINT FLUX
Citation Formats
Favorite, Jeffrey A. SENSMG: First-Order Sensitivities of Neutron Reaction Rates, Reaction-Rate Ratios, Leakage, keff, and α Using PARTISN. United States: N. p., 2016.
Web. doi:10.2172/1333129.
Favorite, Jeffrey A. SENSMG: First-Order Sensitivities of Neutron Reaction Rates, Reaction-Rate Ratios, Leakage, keff, and α Using PARTISN. United States. doi:10.2172/1333129.
Favorite, Jeffrey A. Mon .
"SENSMG: First-Order Sensitivities of Neutron Reaction Rates, Reaction-Rate Ratios, Leakage, keff, and α Using PARTISN". United States.
doi:10.2172/1333129. https://www.osti.gov/servlets/purl/1333129.
@article{osti_1333129,
title = {SENSMG: First-Order Sensitivities of Neutron Reaction Rates, Reaction-Rate Ratios, Leakage, keff, and α Using PARTISN},
author = {Favorite, Jeffrey A.},
abstractNote = {SENSMG is a tool for computing first-order sensitivities of neutron reaction rates, reaction-rate ratios, leakage, keff, and α using the PARTISN multigroup discrete-ordinates code. SENSMG computes sensitivities to all of the transport cross sections and data (total, fission, nu, chi, and all scattering moments), two edit cross sections (absorption and capture), and the density for every isotope and energy group. It also computes sensitivities to the mass density for every material and derivatives with respect to all interface locations. The tool can be used for one-dimensional spherical (r) and two-dimensional cylindrical (r-z) geometries. The tool can be used for fixed-source and eigenvalue problems. The tool implements Generalized Perturbation Theory (GPT) as discussed by Williams and Stacey. Section II of this report describes the theory behind adjoint-based sensitivities, gives the equations that SENSMG solves, and defines the sensitivities that are output. Section III describes the user interface, including the input file and command line options. Section IV describes the output. Section V gives some notes about the coding that may be of interest. Section VI discusses verification, which is ongoing. Section VII lists needs and ideas for future work. Appendix A lists all of the input files whose results are presented in Sec. VI.},
doi = {10.2172/1333129},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Mon Nov 21 00:00:00 EST 2016},
month = {Mon Nov 21 00:00:00 EST 2016}
}
-
Pulse neutron subcritical K/sub EFF/ measurements on water flooded arrays of fuel rods
The pulsed neutron source technique has been utilized at the Pacific Northwest Laboratory for some twenty years for measurement of subcritical reactivities of a variety of fuel systems. One area of application has included measurements of subcritical reactivities of water flooded arrays of fuel rods. This report summarizes these measurements. The theory behind the measurement process is reviewed and the instrumentation of the measurement system discussed. Also, four experiment programs are described in detail, illustrating system use and flexibility. Some changes are suggested for system improvements to speed up data collection and data reduction, and some possible areas of futuremore » -
TEMPERATURE DEPENDENCE OF COMBINED MOLECULAR DIFFUSION AND REVERSIBLE FIRST ORDER CHEMICAL REACTION RATES
A solutuon to differential equations is offered for interphase mass transfer processes in which the component transferred takes part ln a chemical reactdon wmth a component. The solution of these equations for the case of first-order reversible chemical reaction is given and used to predict the temperature dependence of the transfer rates assuming the usual relations of diffusivity and reactivity with temperature. (J.R.D.)