POWER LEVEL EFFECT IN A PWR ROD EJECTION ACCIDENT.

Conference · Mon Oct 07 04:00:00 EDT 2002

OSTI ID:799476

DIAMOND, D J ^[1]; BROMLEY, B P; ARONSON, A L

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1. BROOKHAVEN NATIONAL LABORATORY

The purpose of this study is to determine the effect of the initial power level during a rod ejection accident (REA) on the ejected rod worth and the resulting energy deposition in the fuel. The model used is for the hot zero power (HZP) conditions at the end of a typical fuel cycle for the Three Mile Island Unit 1 pressurized water reactor. PARCS, a transient, three-dimensional, two-group neutron nodal diffusion code, coupled with its own thermal-hydraulics model, is used to perform both steady-state and transient simulations. The worth of an ejected control rod is affected by both power level, and the positions of control banks. As the power level is increased, the worth of a single central control rod tends to drop due to thermal-hydraulic feedback and control bank removal, both of which flatten the radial neutron flux and power distributions. Although the peak fuel pellet enthalpy rise during an REA will be greater for a given ejected rod worth at elevated initial power levels, it is more likely the HZP condition will cause a greater net energy deposition because an ejected rod will have the highest worth at HZP. Thus, the HZP condition can be considered the most conservative in a safety evaluation.

• Research Organization: Brookhaven National Lab., Upton, NY (US)
• Sponsoring Organization: NRC/DOE (US)
• DOE Contract Number: AC02-98CH10886
• OSTI ID: 799476
• Report Number(s): BNL--NUREG-69285; 26015110201
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
CONTROL ELEMENTS
DEPOSITION
DIFFUSION
ENTHALPY
FEEDBACK
FUEL CYCLE
FUEL PELLETS
NEUTRON FLUX
NEUTRONS
POWER DISTRIBUTION
PWR TYPE REACTORS
ROD EJECTION ACCIDENTS
SAFETY
TRANSIENTS