Improvements to the transient solution in the PANTHER space-time code
- Nuclear Electric Company, Gloucestershire (United Kingdom)
The three dimensional, two-group, nodal diffusion code PANTHER has been developed for the analysis of almost all thermal reactor types [pressurized water reactor (PWR), boiling water reactor, VVER, RBMK, advanced gas-cooled reactor, MAGNOX]. It can perform a comprehensive range of calculations for fuel management, operational support including on-line application, and transient analysis. Transient results for a number of light water reactor (LWR) benchmark problems have been reported previously. This paper outlines some recent developments of the transient solution in PANTHER, showing results for two LWR benchmark problems. Recently, PANTHER results have been accepted as the reference solutions for a Nuclear Energy Agency Committee on Reactor Physics (NEACRP) rod ejection benchmark Unlike previous simplified rod ejection benchmarks, it represents a real PWR with a detailed thermal model and cross sections dependent on boron, fuel temperature, and water density and temperature. This reference solution was computed with fine time steps.
- OSTI ID:
- 5884083
- Report Number(s):
- CONF-930601--
- Journal Information:
- Transactions of the American Nuclear Society; (United States), Journal Name: Transactions of the American Nuclear Society; (United States) Vol. 68; ISSN 0003-018X; ISSN TANSAO
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
220100* -- Nuclear Reactor Technology-- Theory & Calculation
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
COMPUTER CODES
COMPUTERIZED SIMULATION
EQUATIONS
FUEL MANAGEMENT
NUMERICAL SOLUTION
P CODES
REACTOR FUELING
REACTOR KINETICS EQUATIONS
REACTOR SAFETY
SAFETY
SIMULATION
THERMAL ANALYSIS