A proposal for an NRU loop irradiation of a canflex bundle containing 1.35% pu mox fuel in the outer and inner rings

A proposal for an NRU loop irradiation of a canflex bundle containing 1.35% pu mox fuel in the outer and inner rings PDF Author: H. B. Hamilton
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Languages : en
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A proposal for an NRU loop irradiation of a canflex bundle containing 1.35% pu mox fuel in the outer and inner rings

A proposal for an NRU loop irradiation of a canflex bundle containing 1.35% pu mox fuel in the outer and inner rings PDF Author: H. B. Hamilton
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Languages : en
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A proposal for an NRU loop irradiation of a "parallex" CANDU-6 geometry bundle containing natural uranium (outer ring) and 3.1% pu in depleted uranium (intermediate/inner rings).

A proposal for an NRU loop irradiation of a Author: M. R. Floyd
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Languages : en
Pages : 0

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A proposal for an NRU loop irradiation of a "parallex" CANDU-6 geometry bundle containing 3.1% pu in depleted uranium (intermediate/inner rings) and 1.25% dy in natural uranium (outer ring).

A proposal for an NRU loop irradiation of a Author: F. C. Dimayuga
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Languages : en
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A proposal for an NRU loop irradiation and power ramp of two canflex mk iv high-burnup low-void-reactivity fuel (hb-LVRF) bundles containing enriched uranium, natural uranium and dysprosium

A proposal for an NRU loop irradiation and power ramp of two canflex mk iv high-burnup low-void-reactivity fuel (hb-LVRF) bundles containing enriched uranium, natural uranium and dysprosium PDF Author: M. R. Floyd
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Languages : en
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Post-irradiation examination of overheated canflex bundles

Post-irradiation examination of overheated canflex bundles PDF Author: D. F. Sears
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Languages : en
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Five canflex fuel bundles were irradiated in the u2 loop in nru during 1990. the 43-element bundles contained two element sizes: 11.5 mm diameter elements with 0.33 mm thin-wall zr-4 cladding in the outer and intermediate rings, and 13.5 mm diameter elements with 0.35 mm thin-wall cladding in the inner ring. three bundles contained uo2 enriched to 2.59% u-235 in u, and two contained natural uo2 in the intermediate and outer ring of elements, with 2.59% enriched uo2 in the inner ring. the bundles overheated when, due to loss of class iv electrical power to the main loop pumps, the coolant flow stagnated briefly in the down leg of the u loop, then reversed direction as convective cooling was established. although the bundle power decayed rapidly after the reactor tripped due to the loss of electrical power, the stored energy and decay heat were sufficient to cause overheating of the bundles during the brief stagnation period, and this in turn led to steam generation which resulted in high coolant pressure (sheath temperature in excess of 600 degrees c and coolant pressure above 11.2 mpa). post-irradiation examinations revealed that the sheath in some elements had collapsed into the gaps between the pellet stack and end caps, and between adjacent pellets; however, no defects were attributed to sheath collapse. two of the elements had defects due to hydride blisters, but the source of the hydrogen was not from a breach in the cladding or end caps. the defects were attributed to primary hydriding. the results show that even though the bundles were subjected to abnormally high temperatures and pressures, and were damaged as a result, none of the collapsed elements leaked. this indicates that thin-wall cladding provides a significant margin of safety during transient high temperature and pressure excursions.

A proposal for an NRU loop irradiation of four canflex bundles to investigate power-ramp thresholds at extended burnup

A proposal for an NRU loop irradiation of four canflex bundles to investigate power-ramp thresholds at extended burnup PDF Author: M. R. Floyd
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Languages : en
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A proposal for an NRU loop irradiation of four canflex bundles to investigate power-ramp thresholds at extended burnup

A proposal for an NRU loop irradiation of four canflex bundles to investigate power-ramp thresholds at extended burnup PDF Author: H. Hamilton
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Languages : en
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Proposal for the irradiation of mox fuel bundles on the s-261 string as u2c-3725 in e-20 with bdl-440 canflex mk iv type bundle akt in the o-17 outlet test section of the u-2 loop

Proposal for the irradiation of mox fuel bundles on the s-261 string as u2c-3725 in e-20 with bdl-440 canflex mk iv type bundle akt in the o-17 outlet test section of the u-2 loop PDF Author: I. A. Lusk
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Languages : en
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Proposal for the continued irradiation of low void, canflex, mox and materials test bundles in the s-240 string as u2c-368 in e-20, with the s-244 fuel string as u2d-525 containing canflex and materials test bundles in the o-17 outlet test section of the u-2 loop

Proposal for the continued irradiation of low void, canflex, mox and materials test bundles in the s-240 string as u2c-368 in e-20, with the s-244 fuel string as u2d-525 containing canflex and materials test bundles in the o-17 outlet test section of the u-2 loop PDF Author: P. G. Anderson
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Languages : en
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Proposal for the irradiation of mox fuel bundles on the s-261 string as u2c-3723 in e-20 with the power ramp of bdl-440 canflex mk iv type bundle akt in the o-17 outlet test section of the u-2 loop

Proposal for the irradiation of mox fuel bundles on the s-261 string as u2c-3723 in e-20 with the power ramp of bdl-440 canflex mk iv type bundle akt in the o-17 outlet test section of the u-2 loop PDF Author: I. A. Lusk
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Category :
Languages : en
Pages : 0

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