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Title: A Parametric Study of the Adjoint Flux Calculation for TDKENO

Abstract

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 pointmore » 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)« less

Authors:
; ;  [1];  [2]
  1. Nuclear Engineering Program, University of Florida 529 Gale Lemerand Dr., Gainesville, FL, 32611 (United States)
  2. Nuclear Systems Design and Analysis Division Idaho National Laboratory, 2525 North Freemont Street, Idaho Falls ID, 83415 (United States)
Publication Date:
OSTI Identifier:
23042859
Resource Type:
Journal Article
Journal Name:
Transactions of the American Nuclear Society
Additional Journal Information:
Journal Volume: 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); Journal ID: ISSN 0003-018X
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 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

Citation Formats

Popp, Dustin, Mausolff, Zander, Goluoglu, Sedat, and DeHart, Mark. A Parametric Study of the Adjoint Flux Calculation for TDKENO. United States: N. p., 2016. Web.
Popp, Dustin, Mausolff, Zander, Goluoglu, Sedat, & DeHart, Mark. A Parametric Study of the Adjoint Flux Calculation for TDKENO. United States.
Popp, Dustin, Mausolff, Zander, Goluoglu, Sedat, and DeHart, Mark. 2016. "A Parametric Study of the Adjoint Flux Calculation for TDKENO". United States.
@article{osti_23042859,
title = {A Parametric Study of the Adjoint Flux Calculation for TDKENO},
author = {Popp, Dustin and Mausolff, Zander and Goluoglu, Sedat and DeHart, Mark},
abstractNote = {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)},
doi = {},
url = {https://www.osti.gov/biblio/23042859}, journal = {Transactions of the American Nuclear Society},
issn = {0003-018X},
number = ,
volume = 115,
place = {United States},
year = {Fri Jul 01 00:00:00 EDT 2016},
month = {Fri Jul 01 00:00:00 EDT 2016}
}