SENSMG: First-Order Sensitivities of Neutron Reaction Rates, Reaction-Rate Ratios, Leakage,keff, andαUsing PARTISN

Favorite, Jeffrey A.

doi:10.1080/00295639.2018.1471296

Cited by 24 publications

(20 citation statements)

References 13 publications

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“…15 Second-and higher-order uncertainty quantification is possible 15 and in fact desirable, because second-order contributions may be larger than one suspects. 16 For deterministic multigroup neutron problems, SENSMG can compute first-order 5,6 and secondorder sensitivities of a neutron response (but not keff) in a one-dimensional sphere or a two-dimensional cylinder (but not a stand-off point response) with respect to a cross section. [16][17][18][19] Cross sections for deterministic gamma-ray calculations are not generally appropriate for INRAD, so PARTISN and SENSMG would not generally be applied.…”

Section: Iia Capabilitiesmentioning

confidence: 99%

“…3 SENSMG can compute first-order sensitivities of keff with respect to a cross section in a one-dimensional sphere or a two-dimensional cylinder. 5,6 MCNP6 has a feature that would be very useful to determine the effect of changing cross-section libraries on keff, the KPERT card, but it has a bug that prevents its use. 23 SENSMG outputs the sensitivity of any response to each nuclide's Legendre scattering moment, 6 so it is easy to determine the relative importance of the scattering moments.…”

Section: Iia Capabilitiesmentioning

confidence: 99%

“…SENSMG can compute the derivative of a response with respect to material interface locations in spheres and cylinders for multigroup neutron fixed-source and keff problems. 5,6 The derivatives describe the change in the response as the interface moves in a direction parallel to its surface normal. 34,35 MCNP had a preliminary capability for computing the keff sensitivity to system dimensions, 36 but there are no plans to put that capability into production.…”

Section: Va Capabilitiesmentioning

confidence: 99%

“…The PARTISN multigroup discrete ordinates code 4 has a well-developed associated sensitivity capability, the SENSMG code. 5,6 There are two drawbacks of using PARTISN and SENSMG: 1) SENSMG is limited to onedimensional spherical and two-dimensional cylindrical geometries; and 2) in the case of twodimensional cylinders, the discrete-ordinates angular treatment cannot be used for stand-off detectors. Nevertheless, the comprehensive sensitivity capabilities of these codes may make them very suitable for INRAD applications, and they are discussed in this report.…”

Section: Introductionmentioning

confidence: 99%

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(U) Radiation Transport Sensitivity Capabilities Applicable to INRAD

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2020

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Section: Iia Capabilitiesmentioning

confidence: 99%

Section: Iia Capabilitiesmentioning

confidence: 99%

Section: Va Capabilitiesmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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(U) Radiation Transport Sensitivity Capabilities Applicable to INRAD

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2020

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“…There is no absolute reaction rate in a critical system unless the amplitude of the flux is (  in the equations of this section, particularly Eqs. (4), (9), and (15). In the SENSMG sensitivity tool, we use 1 for g P  so that P becomes the flux in the reactionrate region.…”

Section:  Fmentioning

confidence: 99%

(U) SENSMG: First-Order Sensitivities of Neutron Reaction Rates, Reaction-Rate Ratios, Leakage, keff, α, and Subcritical Multiplication Using PARTISN

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2019

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SENSMG is a tool for computing first-order sensitivities of neutron reaction rates, reaction-rate ratios, leakage, keff, α, and subcritical multiplication using the PARTISN multigroup discrete-ordinates code. 1 SENSMG computes sensitivities to all of the transport cross sections and data (total, fission, a nu, chi, and all scattering moments), four edit cross sections (absorption, capture, elastic scattering, and inelastic scattering), 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 and outer boundaries. The tool can be used for one-dimensional spherical and slab (r) and two-dimensional cylindrical (r-z) geometries. The tool can be used for fixed-source and eigenvalue problems. For most responses, the tool implements Generalized Perturbation Theory (GPT) as discussed by Williams 2 and Stacey. 3 The tool is thus limited to computing sensitivities only for GPT-allowable responses. 4 For subcritical multiplication, the tool implements sensitivities derived by O'Brien 5 and Clark. 6 SENSMG has a similar role as the old SWANLAKE (Ref. 7), FORSS (Ref. 8), and SENSIT (Ref. 9) codes. It has capabilities similar to those of SUSD3D (Ref. 10), which also uses PARTISN. 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 presents some sample problems and discusses verification, which is ongoing. Section VII lists needs and ideas for future work. Appendix A lists most of the input files whose results are presented in Sec. VI. Appendix B provides some useful details on one of the cross-section libraries that SENSMG supports. a Technically, fission is an edit cross section in PARTISN because only the product with nu is used in the transport.

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Expert‐in‐the‐loop design of integral nuclear data experiments

Michaud,

Grosskopf,

Hutchinson

et al. 2024

Statistical Analysis

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Nuclear data are fundamental inputs to radiation transport codes used for reactor design and criticality safety. The design of experiments to reduce nuclear data uncertainty has been a challenge for many years, but advances in the sensitivity calculations of radiation transport codes within the last two decades have made optimal experimental design possible. The design of integral nuclear experiments poses numerous challenges not emphasized in classical optimal design, in particular, constrained design spaces (in both a statistical and engineering sense), severely under‐determined systems, and optimality uncertainty. We present a design pipeline to optimize critical experiments that uses constrained Bayesian optimization within an iterative expert‐in‐the‐loop framework. We show a successfully completed experiment campaign designed with this framework that involved two critical configurations and multiple measurements that targeted compensating errors in 239Pu nuclear data.

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SENSMG: First-Order Sensitivities of Neutron Reaction Rates, Reaction-Rate Ratios, Leakage,k_eff, andαUsing PARTISN

Cited by 24 publications

References 13 publications

(U) Radiation Transport Sensitivity Capabilities Applicable to INRAD

(U) Radiation Transport Sensitivity Capabilities Applicable to INRAD

(U) SENSMG: First-Order Sensitivities of Neutron Reaction Rates, Reaction-Rate Ratios, Leakage, k<sub>eff</sub>, α, and Subcritical Multiplication Using PARTISN

Expert‐in‐the‐loop design of integral nuclear data experiments

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