The advanced nodal transient analysis code ARROTTA
- Electric Power Research Institute, Palo Alto, CA (USA)
The Electric Power Research Institute (EPRI) has sponsored the development of the three-dimensional reactor kinetics code ARROTTA under project RP-1936. The neutronics formalism is based on the QUANDRY methodology developed at Massachusetts Institute of Technology. The thermal hydraulics was developed at Brookhaven National Laboratory and incorporated into the BEAGL program. Recently, the advanced EPRI thermal-hydraulic code VIPRE-2 has been coupled to ARROTTA to provide an alternate and more accurate simulation of the hydraulic phenomena, including crossflow. The current ARROTTA thermal-hydraulic model uses a two-phase fluid model that describes the one-dimensional, time-dependent mass and energy conservation equations in each channel separately under a single pressure assumption and without crossflow. ARROTTA is intended for static and transient calculations as a branch initialized from some depletion point of a standard core-follow procedure. Thus, the same core cycle data-base generator that provides input to standard static nodal codes routinely used in pressurized water reactor (PWR) and boiling water reactor (BWR) core representation also provides the data base processed by the ARROTTA input generator, which is a revision of the BLEND code.
- OSTI ID:
- 6179228
- 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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22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
A CODES
ACCURACY
B CODES
BENCHMARKS
BNL
BWR TYPE REACTORS
COMPUTER CODES
CROSS SECTIONS
ENERGY TRANSFER
EPRI
FLUID FLOW
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
KINETICS
MECHANICS
MULTIGROUP THEORY
NATIONAL ORGANIZATIONS
NEUTRON TRANSPORT THEORY
NODAL EXPANSION METHOD
PHYSICS
PWR TYPE REACTORS
REACTOR KINETICS
REACTOR PHYSICS
REACTOR SAFETY
REACTORS
SAFETY
TESTING
THREE-DIMENSIONAL CALCULATIONS
TRANSPORT THEORY
TWO-PHASE FLOW
US AEC
US DOE
US ERDA
US ORGANIZATIONS
V CODES
VALIDATION
WATER COOLED REACTORS
WATER MODERATED REACTORS