A Parametric Study of the Adjoint Flux Calculation for TDKENO
- Nuclear Engineering Program, University of Florida 529 Gale Lemerand Dr., Gainesville, FL, 32611 (United States)
- Nuclear Systems Design and Analysis Division Idaho National Laboratory, 2525 North Freemont Street, Idaho Falls ID, 83415 (United States)
TDKENO is a time-dependent transport code designed to simulate reactor transients. One application is to study experiments performed at the Transient Reactor Test Facility (TREAT) at the Idaho National Laboratory (INL). TDKENO solves the time-dependent, three-dimensional Boltzmann transport equation with explicit representation of delayed neutrons. Instead of directly integrating this equation, the Improved Quasi Static (IQS) method is employed. This involves factoring the neutron flux into two components - a rapidly varying (in time) amplitude equation and a slowly varying shape equation. These are solved separately on different time scales. The shape equation is solved using the Monte Carlo transport code KENO, from Oak Ridge National Laboratory's SCALE code package. Using the Monte Carlo method to solve the shape equation is computationally intensive, but the operation is only performed when needed - namely when the reactor system is undergoing a significant change. The amplitude equation is solved deterministically. This operation contains the time dependence and can be calculated relatively quickly, resulting in computational savings. TDKENO begins by solving the adjoint form of the transport equation for use as a weighting function. It uses this adjoint flux for multiple aspects of the simulation, including the calculation of all of the point kinetics parameters . The flux shape is found by solving a modified form of the transport equation in 'forward' mode. This paper examines the effect the adjoint weighting function has on the solution. (authors)
- OSTI ID:
- 23042859
- Journal Information:
- Transactions of the American Nuclear Society, Vol. 115; Conference: 2016 ANS Winter Meeting and Nuclear Technology Expo, Las Vegas, NV (United States), 6-10 Nov 2016; Other Information: Country of input: France; 10 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US); ISSN 0003-018X
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
ADJOINT FLUX
BOLTZMANN EQUATION
COMPUTERIZED SIMULATION
DELAYED NEUTRONS
KINETICS
MONTE CARLO METHOD
PARAMETRIC ANALYSIS
REACTOR DESIGN
REACTOR OPERATION
THREE-DIMENSIONAL CALCULATIONS
TIME DEPENDENCE
TRANSIENTS
TRANSPORT THEORY
TREAT REACTOR
WEIGHTING FUNCTIONS