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The development of a transient neutron flux solution in the PANTHER code

Conference · · Transactions of the American Nuclear Society; (USA)
OSTI ID:6180880
;

In the United Kingdom a new three-dimensional, two-group, homogeneous reactor diffusion code, PANTHER, has been developed for the analysis of pressurized water reactors (PWRs) and advanced gas-cooled reactors (AGRs). The code can perform a comprehensive range of calculations, steady state, depletion, and transient with either a finite difference or analytic nodal flux solution. The nodal solution allows the representation of within-node burnup variation and pin-power reconstruction in either steady-state or transient mode. Specific steady-state and transient thermal feedback modules are included for both PWRs and AGRs. The code is being developed to perform a complete range of reactor calculations from online operational support to fuel management and fault transient analysis. In the area of transient analysis, the code is currently being used for a number of PWR fault transient assessments, including rod ejection and steam-line break. In addition, work is proceeding to incorporate the PANTHER 3D nodal transient solution in the TRAC-P code. This paper outlines the development of the transient flux solutions within PANTHER.

OSTI ID:
6180880
Report Number(s):
CONF-900608--
Journal Information:
Transactions of the American Nuclear Society; (USA), Journal Name: Transactions of the American Nuclear Society; (USA) Vol. 61; ISSN TANSA; ISSN 0003-018X
Country of Publication:
United States
Language:
English

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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
ACCURACY
ALGORITHMS
BENCHMARKS
BURNUP
COMPUTER CODES
COMPUTERIZED SIMULATION
DIFFERENTIAL EQUATIONS
EQUATIONS
EUROPE
FINITE DIFFERENCE METHOD
FUEL MANAGEMENT
ITERATIVE METHODS
MATHEMATICAL LOGIC
MULTIGROUP THEORY
NEUTRON DIFFUSION EQUATION
NEUTRON TRANSPORT THEORY
NUMERICAL SOLUTION
OPERATION
P CODES
PHYSICS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR CORES
REACTOR OPERATION
REACTOR PHYSICS
REACTORS
SIMULATION
STEADY-STATE CONDITIONS
T CODES
THREE-DIMENSIONAL CALCULATIONS
TRANSIENTS
TRANSPORT THEORY
UNITED KINGDOM
WATER COOLED REACTORS
WATER MODERATED REACTORS
WESTERN EUROPE