Static Generalized Perturbation Theory with Feedback Effects and Criticality Reset

Conference · Sun Jun 15 04:00:00 EDT 1986 · Transactions of the American Nuclear Society

OSTI ID:6662299

White, J. R. ^[1]; Frank, B. R. ^[1]

---

1. University of Lowell, HaverHill, MA (United States)

The primary emphasis in the application of generalized perturbation theory (GPT) methods to date has been in the computation of cross-section sensitivities. These data sensitivity coefficients have been used extensively to evaluate the uncertainty of fast reactor performance parameters and to quantify the need for further nuclear data measurements. However, some recent work associated with the development of a GPT-based fuel management optimization algorithm has shown that perturbation methods can also play an important role in the engineering design of light water reactor (LWR) reload cores. These GPT methods, however, must be adapted to reflect current LWR design practices. In particular, the reactor must be kept critical, and the effects of thermal-hydraulic feedback must be considered. Although criticality reset techniques (or k-reset) have been addressed previously, there does not appear to be any comprehensive GPT development that accounts for the indirect coupling (through feedback mechanisms) of the macroscopic cross sections to the neutron flux or reactor power distribution. The purpose of this paper is to present such a development - a static GPT formulation that includes feedback effects and k-reset. The approach taken here is to define a variational principle that includes these phenomena as constraint equations appended to the response functional using Lagrange multipliers.

• Research Organization: University of Lowell, HaverHill, MA (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• OSTI ID: 6662299
• Report Number(s): CONF-860610-
• Conference Information: Journal Name: Transactions of the American Nuclear Society Journal Volume: 52
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
97 MATHEMATICS AND COMPUTING
BWR TYPE REACTORS
COMPUTERIZED SIMULATION
CRITICALITY
ENERGY TRANSFER
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
MECHANICS
Nuclear Criticality Safety Program (NCSP)
PERFORMANCE
PERTURBATION THEORY
PHYSICS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR CORES
REACTOR PHYSICS
REACTORS
SIMULATION
WATER COOLED REACTORS
WATER MODERATED REACTORS