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JAEA Reports

Experimental data in DCA (15) Micro-parameters at 25.0 cm pitch lattice

*; *; *; *; *

PNC TN941 79-195, 66 Pages, 1979/10

PNC-TN941-79-195.pdf:2.06MB

Micro-parameters have been measured in plutonium fuel loaded in 25.0 cm pitch lattice. The fuels used for the measurements were 0.54 w/o PuO$$_{2}$$ (standard grade)-UO$$_{2}$$[5SPu] and 0.87 w/o PuO$$_{2}$$ (reactor grade)-UO$$_{2}$$[8RPu]. The "coolants" used in the experiment on 5S Pu fuel lattice were H$$_{2}$$O [0% void], mixture of H$$_{2}$$O, D$$_{2}$$O and H3BO$$_{4}$$ [30% void], and Air [100% void]. In the case 8R Pu fuel, H$$_{2}$$O and Air were used as the coolants. The measurements were also done on the lattice of 0% void fraction with 3.9 $$^{10}$$B ppm in D$$_{2}$$O moderator loaded with 5S Pu fuel to investigate the effect of $$^{10}$$B in the moderator. The micro-parameters such as $$rho$$$$^{28}$$, $$delta$$$$^{25}$$, $$delta$$$$^{49}$$, $$delta$$$$^{28}$$ and $$delta$$$$^{49}$$$$_{25}$$ were obtained by the foil activation method in using plutonium-foils, enriched-uranium-foils, natural uranium foils and depleted uranium foils. The micro-parameters measured in the DCA's lattices are shown in the following table.

JAEA Reports

Measurements of intra-cell thermal neutron flux distributions in plutonium fuel lattices; Experiment on 25.0 cm pitch lattice

*; *; *; *; *; Hachiya, Yuki*

PNC TN941 79-149, 76 Pages, 1979/09

PNC-TN941-79-149.pdf:1.5MB

Intra-cell thermal neutron flux distributions have been measured in plutonium fuel lattices at 25.0 cm pitch by means of dysprosium foil activation method. Enrichments of PuO$$_{2}$$ in PuO$$_{2}$$-UO$$_{2}$$ fuels used are 0.54 wt% and 0.87 wt%. The measurements on 0.54 wt% enriched Pu0$$_{2}$$-UO$$_{2}$$ fuel lattices were made using air, light water or D$$_{2}$$O-H$$_{2}$$O-H$$_{3}$$BO$$_{3}$$ mixture containg $$sim$$ 37 wt% of D$$_{2}$$O, as coolants. Those on 0.87 wt% enriched PuO$$_{2}$$-UO$$_{2}$$ fuel lattices were made using air or light water. The effect of $$^{10}$$B in D$$_{2}$$O moderator on the thermal neutron flux distribution was also investigated in 0.54 wt% enriched PuO$$_{2}$$-UO$$_{2}$$ fuel lattice with H$$_{2}$$O coolant and D$$_{2}$$O moderator containg $$^{10}$$B by 3.9 ppm. Measurement uncertainty in the present experiment is $$pm$$2 %, which is almost the same as that in the experiment on plutonium lattices at 22.5 cm pitch. To scrutinize dependence of flux distribution on lattice pitch, the results of the present experiment were compared with those of the experiments on 22.5 cm-pitch lattices which had been already made. The calculations by the code LAMP-DCA agrees with the experiment within $$sim$$ 2 %.

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