Bounding burnout risk power limits for the K-14 cycle
This document discusses burnout risk (BOR) power limits which are designed to protect the reactor from a significant release of fission products, due to critical heat flux (CHF) burnout of fuel and target assemblies. At expected operating power levels for the reactor restart, approximately 50% of historical full power, the risk of CHF and attendant burnout is negligible. Flow instability power limits will restrict reactor operation, and flow instability will always occur before CHF. BOR power limits must nevertheless be calculated because they are required by the reactor control computer, (2) Bounding BOR limits have been calculated for the K-14 cycle, to fulfill this requirement, and they are presented in this document. Two sets of BOR limits have been calculated: one applicable for the first subcycle, zero to 30% fuel burnup, and the other for the second subcycle, 30% to 55% fuel burnup.
- Research Organization:
- Savannah River Site (SRS), Aiken, SC (United States)
- Sponsoring Organization:
- USDOE; USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC09-89SR18035
- OSTI ID:
- 5141823
- Report Number(s):
- WSRC-TR-90-394; ON: DE92015062
- Country of Publication:
- United States
- Language:
- English
Similar Records
Critical heat flux concerns during the flow instability phase of a DEGB LOCA
Critical heat flux concerns during the flow instability phase of a DEGB LOCA
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
PRODUCTION REACTORS
BURNOUT
CRITICAL HEAT FLUX
F CODES
FUEL ELEMENTS
HEAT TRANSFER
HYDRAULICS
LIMITING VALUES
LOSS OF COOLANT
MATHEMATICAL MODELS
REACTOR SAFETY
SAVANNAH RIVER PLANT
ACCIDENTS
COMPUTER CODES
ENERGY TRANSFER
FLUID MECHANICS
HEAT FLUX
MECHANICS
NATIONAL ORGANIZATIONS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
SAFETY
US AEC
US DOE
US ERDA
US ORGANIZATIONS
220900* - Nuclear Reactor Technology- Reactor Safety
220600 - Nuclear Reactor Technology- Research
Test & Experimental Reactors