Analysis of small-sample reactivity worths in the Fast Test Reactor Engineering Mockup Critical
Small-sample reactivity worths were computed and compared with measurements at core center and along a radial traverse of the Fast Test Reactor Engineering Mockup Critical (FTR-EMC). The computed worths were obtained with first order perturbation theory using real and adjoint neutron fluxes from 42-group X-Y diffusion theory calculations. The perturbation denominator (importance-weighted neutron production rate) was obtained from three-dimensional X-Y-Z calculations. For most of the calculated worths, cross sections were from the FTR Set 300S library (essentially ENDF/B version III data); however, ENDF/B version IV delayed neutron parameters were used to generate the necessary conversion factor to allow comparison of measured and calculated worths. At core center the C/E values were 1.14 to 1.33 for plutonium samples, 1.11 for a depleted uranium sample, 0.97 to 1.05 for boron, 0.89 to 1.08 for europia, 1.4 for stainless steel and 2.6 for iron oxide.
- Research Organization:
- Hanford Engineering Development Lab., Richland, Wash. (USA)
- DOE Contract Number:
- EY-76-C-14-2170
- OSTI ID:
- 7231232
- Report Number(s):
- HEDL-TME-76-87
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
ACTINIDES
ALLOYS
BORON
CHROMIUM ALLOYS
CORROSION RESISTANT ALLOYS
ELEMENTS
EPITHERMAL REACTORS
EUROPIUM
FAST REACTORS
FFTF REACTOR
IRON
IRON ALLOYS
IRON BASE ALLOYS
LIQUID METAL COOLED REACTORS
METALS
MOCKUP
PLUTONIUM
RARE EARTHS
REACTIVITY WORTHS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SEMIMETALS
SODIUM COOLED REACTORS
STAINLESS STEELS
STEELS
STRUCTURAL MODELS
TEST REACTORS
TRANSITION ELEMENTS
TRANSURANIUM ELEMENTS
URANIUM