A Benchmark for Investigating the Radial Dependence of C/E for Control Rod Worths in Large Decoupled Cores

Conference · Mon Apr 23 00:00:00 EDT 1990

OSTI ID:7157687

Salvatores, M ^[1]; Orechwa, Y. ^[2]; Collins, P. J. ^[3]

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1. Commissariat a l'Energie Atomique et aux Energies Alternatives (CEA), Cadarache (France)
2. Argonne National Laboratory (ANL), Argonne, IL (United States)
3. Argonne National Laboratory, Idaho Falls, ID (United States)

The first physics measurements of a heterogeneous core on the critical assembly ZPPR-7 at ANL showed that the C/E ratios with ENDF/B data for the worths of the control rods in the outer bank were several percent higher than those at the inner bank positions. This radial variation in the C/E for the rod worths was further confirmed in the analysis of the large conventional core ZPPR-10, and again in the analysis of the large heterogeneous core series ZPPR-13. In the design of a power reactor, the number of control rods, and their disposition, are determined by calculations. Misprediction of the worth of the control rods can lead to serious economic penalties by restricting the operation of the core. Retrofitting a core to accommodate more worth will be costly and is likely to lead to a non-optimized core. This document provides a discussion of these calculations.

• Research Organization: Alternative Energies and Atomic Energy Commission (CEA), Cadarache (France); Argonne National Laboratory (ANL), Argonne, IL (United States); Argonne National Lab., Idaho Falls, ID (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 7157687
• Report Number(s): CONF-900418-6; ON: DE90007798; TRN: 90-008871
• Resource Relation: Conference: PHYSOR '90: International Conference on the Physics of Reactors: Operation, Design and Computation, Marseilles (France), 23-26 Apr 1990
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
LMFBR TYPE REACTORS
CONTROL ROD WORTHS
REACTOR CORES
BENCHMARKS
COMPARATIVE EVALUATIONS
COMPILED DATA
CRITICALITY
CROSS SECTIONS
E CODES
HETEROGENEOUS EFFECTS
MATHEMATICAL MODELS
REACTOR KINETICS
ZPPR REACTOR
BREEDER REACTORS
COMPUTER CODES
DATA
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
INFORMATION
KINETICS
LIQUID METAL COOLED REACTORS
NUMERICAL DATA
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
ZERO POWER REACTORS
Nuclear Criticality Safety Program (NCSP)
Zero Power Physics Reactor (ZPPR)
Evaluated Nuclear Data File (ENDF)
Control Rods
Critical Assembly
Single-Fuel-Column
Double-Fuel-Column
Internal and Radial Blanket
Axial Blanket
Steel Reflector
Poison Safety Rods (PSRs)
Fuel Rings
220400* - Nuclear Reactor Technology- Control Systems
220900 - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
Breeding
220100 - Nuclear Reactor Technology- Theory & Calculation