PWR benchmarking of ARROTTA at beginning of life
The advanced nodal code ARROTTA can perform multidimensional core analysis for a wide variety of both slow and rapid light water reactor (LWR) transients, as well as criticality searches and eigenvalue calculations. It recently has played the central role in the analysis of a pressurized water reactor (PWR) natural circulation transient without scram occurring at beginning of life (BOL). The severity of that transient was shown to be quite sensitive to the behavior of the moderator temperature coefficient (MTC) of reactivity; therefore, it is of considerable importance that the MTC be calculated very accurately. The present study extends that benchmarking to several additional PWRs and includes comparisons with reference results for isothermal temperature coefficients (ITCs) of reactivity. These reference results are provided either by fine-mesh, quarter-core PDQ7-E calculations or by measurements at operating plants. The ARROTTA code has been shown to predict eigenvalues, nodal power distributions, critical soluble boron concentrations, and ITCs that are in extremely good agreement with measured data and reference results for a variety of core designs at BOL. Furthermore, the accuracy with which ARROTTA calculates these parameters represents a significant improvement relative to one-group and one-and-a-half group nodal codes, which currently are widely used throughout the nuclear industry.
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- OSTI ID:
- 5916550
- Report Number(s):
- CONF-881011-
- Journal Information:
- Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 57; ISSN TANSA; ISSN 0003-018X
- Publisher:
- American Nuclear Society
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
A CODES
ACCURACY
ACTINIDES
ARROTTA
BENCHMARKS
BORON
Beginning of Life (BOL)
CALCULATION METHODS
CE STANDARD REACTOR
COMPUTER CODES
CONTROL ELEMENTS
CONVECTION
COOLING SYSTEMS
CRITICALITY
CROSS SECTIONS
DESIGN
EIGENVALUES
ELEMENTS
ENERGY SYSTEMS
ENERGY TRANSFER
ENRICHED URANIUM
EPRI
FLUID MECHANICS
FUEL ASSEMBLIES
GROUP THEORY
HEAT TRANSFER
HYDRAULICS
ISOTOPE ENRICHED MATERIALS
Isothermal Temperature Coefficients (ITCs)
KINETICS
MASS TRANSFER
MATERIALS
MATHEMATICS
MECHANICS
METALS
MODERATING RATIO
MODERATORS
Moderator Temperature Coefficient (MTC)
NATURAL CONVECTION
NUCLEAR POISONS
Nuclear Criticality Safety Program (NCSP)
POWER DENSITY
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
Pressurized Water Reactor (PWR)
Quarter-Core PDQ7-E Calculations
REACTIVITY
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTOR KINETICS
REACTOR MATERIALS
REACTORS
SEMIMETALS
SENSITIVITY
SLIGHTLY ENRICHED URANIUM
SOLUBLE POISONS
STEADY-STATE CONDITIONS
TRANSIENTS
URANIUM
WATER COOLED REACTORS
WATER MODERATED REACTORS
WESTINGHOUSE STANDARD REACTOR