High /sup 240/Pu FTR/EMC experiments and analysis: Carbide fuel and UO/sub 2/ blanket subassembly worths
Carbide-plutonium fuel and UO/sub 2/ blanket subassembly worth measurements performed at ANL in the EMC/LWR were analyzed. Composition exchange worth calculations were performed for: (a) the replacement of high-/sup 240/Pu fuel composition for low-/sup 240/Pu fuel composition and carbide-plutonium fuel composition, successively, in the center subassembly of the core; (b) the replacement of low-/sup 240/Pu fuel composition for carbide--plutonium fuel composition in one outer driver subassembly; and (c) the replacement of the radial reflector composition with UO/sub 2/ blanket composition in one subassembly of the radial reflector. The composition exchange worth calculations were performed in two-dimensional x,y geometry, using diffusion theory and perturbation theory. Each method produces about the same calculated-to-experimental bias factors.
- Research Organization:
- Hanford Engineering Development Lab., Richland, Wash. (USA)
- DOE Contract Number:
- EY-76-C-14-2170
- OSTI ID:
- 7288850
- Report Number(s):
- HEDL-TME-77-44
- Country of Publication:
- United States
- Language:
- English
Similar Records
High-/sup 240/Pu fuel worth in the Fast Test Reactor Engineering Mockup
Central fuel worth in the Fast Test Reactor (FTR) engineering mockup
ZPR-6 assembly 7 high {sup 240}Pu core experiments : a fast reactor core with mixed (Pu,U)-oxide fuel and a centeral high{sup 240}Pu zone.
Technical Report
·
Tue Dec 31 23:00:00 EST 1974
·
OSTI ID:7348293
Central fuel worth in the Fast Test Reactor (FTR) engineering mockup
Conference
·
Tue Dec 31 23:00:00 EST 1974
·
OSTI ID:7283924
ZPR-6 assembly 7 high {sup 240}Pu core experiments : a fast reactor core with mixed (Pu,U)-oxide fuel and a centeral high{sup 240}Pu zone.
Technical Report
·
Sun Feb 22 19:00:00 EST 2009
·
OSTI ID:948806
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
CHEMICAL COMPOSITION
CONFIGURATION
EPITHERMAL REACTORS
FAST REACTORS
FFTF REACTOR
FUEL ASSEMBLIES
LIQUID METAL COOLED REACTORS
QUANTITY RATIO
REACTIVITY WORTHS
REACTOR COMPONENTS
REACTOR CORES
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SIMULATION
SODIUM COOLED REACTORS
TEST REACTORS
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
CHEMICAL COMPOSITION
CONFIGURATION
EPITHERMAL REACTORS
FAST REACTORS
FFTF REACTOR
FUEL ASSEMBLIES
LIQUID METAL COOLED REACTORS
QUANTITY RATIO
REACTIVITY WORTHS
REACTOR COMPONENTS
REACTOR CORES
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SIMULATION
SODIUM COOLED REACTORS
TEST REACTORS