skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: LOFT fuel prototypes, models, and mockups

Abstract

The report provides a list of and information concerning the prototypes, models, and mockups that were constructed for LOFT Fuel design verification tests, proof-of-fabrication demonstrations, and operator training qualifications.

Authors:
Publication Date:
Research Org.:
Idaho National Engineering Lab., Idaho Falls (USA)
OSTI Identifier:
6588506
Alternate Identifier(s):
OSTI ID: 6588506
Report Number(s):
LTR-1111-46
TRN: 79-000194
DOE Contract Number:
EY-76-C-07-1570
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; LOFT REACTOR; FUEL ELEMENTS; DESIGN; MOCKUP; PERFORMANCE TESTING; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; STRUCTURAL MODELS; TANK TYPE REACTORS; TEST REACTORS; TESTING; WATER COOLED REACTORS; WATER MODERATED REACTORS 220600* -- Nuclear Reactor Technology-- Research, Test & Experimental Reactors

Citation Formats

Russell, M.L. LOFT fuel prototypes, models, and mockups. United States: N. p., 1978. Web. doi:10.2172/6588506.
Copy to clipboard
Russell, M.L. LOFT fuel prototypes, models, and mockups. United States. doi:10.2172/6588506.
Copy to clipboard
Russell, M.L. Thu . "LOFT fuel prototypes, models, and mockups". United States. doi:10.2172/6588506. https://www.osti.gov/servlets/purl/6588506.
Copy to clipboard
@article{osti_6588506,
title = {LOFT fuel prototypes, models, and mockups},
author = {Russell, M.L.},
abstractNote = {The report provides a list of and information concerning the prototypes, models, and mockups that were constructed for LOFT Fuel design verification tests, proof-of-fabrication demonstrations, and operator training qualifications.},
doi = {10.2172/6588506},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Thu Jul 27 00:00:00 EDT 1978},
month = {Thu Jul 27 00:00:00 EDT 1978}
}
Copy to clipboard
Technical Report:
View Technical Report (0.53 MB)
DOI:  10.2172/6588506
Save / Share:
Export Metadata
Save to My Library
You must Sign In or Create an Account in order to save documents to your library.

  • The exhaust of power and fusion-reaction products from ITER plasma are critical physics and technology issues from performance, safety, and reliability perspectives. Because of inadequate pulse length, fluence, flux, scrape-off layer plasma temperature and density, and other parameters, the present generation of tokamaks, linear plasma devices, or energetic beam facilities are unable to perform adequate technology testing of divertor components, though they are essential contributors to many physics issues such as edge-plasma transport and disruption effects and control. This Technical Requirements Documents presents a description of the capabilities and parameters divertor test facilities should have to perform accelerated life testingmore » on predominantly technological divertor issues such as basic divertor concepts, heat load limits, thermal fatigue, tritium inventory and erosion/redeposition. The cost effectiveness of such divertor technology testing is also discussed.« less

  • The exhaust of power and fusion-reaction products from ITER plasma are critical physics and technology issues from performance, safety, and reliability perspectives. Because of inadequate pulse length, fluence, flux, scrape-off layer plasma temperature and density, and other parameters, the present generation of tokamaks, linear plasma devices, or energetic beam facilities are unable to perform adequate technology testing of divertor components, though they are essential contributors to many physics issues such as edge-plasma transport and disruption effects and control. This Technical Requirements Documents presents a description of the capabilities and parameters divertor test facilities should have to perform accelerated life testingmore » on predominantly technological divertor issues such as basic divertor concepts, heat load limits, thermal fatigue, tritium inventory and erosion/redeposition. The cost effectiveness of such divertor technology testing is also discussed.« less

  • ; ;
    LOFT thermocouple response data are presented from the first zircaloy clad heater rod tests conducted in the Blowdown Facility which were intended to simulate coolant and cladding temperature conditions expected during the LOFT loss-of-coolant experiments. Comparison is made to previous stainless steel clad heater rod tests and discussion of the application of these results for correcting LOFT cladding temperature measurements is presented.

  • ; ;
    This report presents the comparison between LOFT type thermocouples (surface mounted) and embedded thermocouples placed in comparable locations on stainless steel clad electrically heated rod. The experiments performed on this rod simulated a hot leg break loss-of-coolant accident (LOCA) with the rods at a high steady state power level. The maximum steady state linear heat generation rate (MLHGR) was 19 kW/ft and the peak cladding temperatures ranged from 1200 to 1600/sup 0/F, thus these experiments are representative of high power LOCA conditions. The purpose of the test was to determine the difference in temperature measured by the two types ofmore » thermocouples and from this to infer how well the LOFT thermocouple measures the surface temperature of a nuclear rod.« less

  • ;
    This report summarizes the measured cladding temperature response during the LOFT L2-2 and L2-3 tests with particular emphasis on both the early cladding quench which occurred during the first 6 to 10 seconds of the transients and the final fuel rod quench resulting from reflooding of the core with ECC water. Supporting analysis work is also presented to aid in understanding the data. A discussion of the measurement errors of the LOFT cladding thermocouples is presented with emphasis on recent separate effects tests. A knowledge of the thermocouple cooling effects based on these separate effects tests is used to estimatemore » an upper bound temperature response for the L2-3 test, which indicates that an uninstrumented LOFT fuel rod may have experienced peak cladding temperatures nearly 100/sup 0/K higher than indicated by the cladding temperature measurements. In addition, unistrumented LOFT fuel rods may have experienced quench during the final reflooding of the core by as much as 25 seconds later than indicated by the cladding thermocouples.« less