Neutronic depletion benchmark problems

Conference · Thu Jan 01 00:00:00 EST 1976

OSTI ID:7343692

Gregory, M. V.; Weate, B. A.; Wagner, M. R.

Three computational benchmark problems are formulated for testing techniques used in the solution of the set of coupled, first-order differential equations termed the neutronic depletion equations. The problems are defined in such a fashion that the techniques used in treating increasingly more complex formulations of the neutronic depletion equations may be examined individually. At the simplest level, the depletion equations may be formulated at a point and with constant coefficients. The Constant Parameter Point Depletion Problem treats this case. At the next level of complexity, the point equations may be written with variable coefficients. This case is treated by the Time-Dependent Point Depletion Problem. The most complex level requires the solution of the set of variable coefficient equations for an entire reactor. This level is treated by the Time-Dependent Reactor Depletion Problem. Solutions for the three problems are presented. The Constant Parameter Problem has time-independent solutions in agreement to within 0.01 percent in the isotopic concentrations at 50 days. The two more-complex problems are still under evaluation. Full problem definitions are presented in the appendices to encourage additional contributed solutions.

• Research Organization: Du Pont de Nemours (E.I.) and Co., Aiken, S.C. (USA). Savannah River Lab.
• DOE Contract Number: E(07-2)-1
• OSTI ID: 7343692
• Report Number(s): DP-MS-76-2; CONF-760622-36; TRN: 77-002084
• Resource Relation: Conference: American Nuclear Society 1976 annual meeting, Toronto, Ontario, Canada, 13 Jun 1976
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
BURNUP
COMPUTER CALCULATIONS
NUCLEAR FUELS
CROSS SECTIONS
ISOTOPE RATIO
MULTIGROUP THEORY
NEUTRON FLUX
REACTOR KINETICS
ENERGY SOURCES
FUELS
KINETICS
NEUTRON TRANSPORT THEORY
RADIATION FLUX
REACTOR MATERIALS
TRANSPORT THEORY
220300* - Nuclear Reactor Technology- Fuel Elements