Limits on the experimental simulation of nuclear fuel rod response. [PWR]

Conference · Tue Jan 01 00:00:00 EST 1980

OSTI ID:6764004

Hagar, R. C.

The steady-state and transient effects of intrinxic geometric and material property differences between typical nuclear fuel pins and electric fuel pin simulators (FPSs) are identified. The effectiveness of varying the transient power supplied to the FPS in reducing the differences between the transient responses of nuclear fuel pins and FPSs is investigated. This effectiveness is shown to be limited by the heat capacity of the FPS, the allowed range of the power program, and different FPS power requirements at different positions on a full-length FPS.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 6764004
• Report Number(s): CONF-801091-9; TRN: 81-000146
• Resource Relation: Conference: International symposium on fuel rod simulators-development and application, Gatlinburg, TN, USA, 22 Oct 1980
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
FUEL RODS
HEATERS
PERFORMANCE
LOSS OF COOLANT
TEST FACILITIES
PWR TYPE REACTORS
ACCURACY
COMPUTER CALCULATIONS
REACTOR SAFETY
SIMULATION
ACCIDENTS
FUEL ELEMENTS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled