A Conceptual Design of a Fuel Bundle for Extended Burnup in Boiling Water Reactors

Aoyama, Motoo; Uchikawa, Sadao; Miki, Kazuyoshi; Hiramoto, Kazuo; Takeda, Renzo

doi:10.13182/nt84-a33323

“…The previous paper< 9 ) showed that the change in the moderator-to-fuel ratio can control the neutron energy spectrum in the fuel bundles and offer desirable values of cold shutdown reactivity and reactivity coefficients. Therefore, it is our intent to keep the same control rod worth as the current designs for the design concept of extended burnup fuel bundles.…”

Section: Fig 1 Configuration Of Current Fuel Bundlementioning

confidence: 99%

“…It is necessary for extended burnup fuel bundles to have the same characteristics as the current fuel bundle design, considering backfit to existing BWR cores. A new fuel bundle design concept< 9 ' for extended burnup, which is characterized by a reduction in maxi-* Moriyama-cho. mum fuel temperature and an increase in moderator-to-fuel ratio, was proposed accordingly.…”

Section: Introductionmentioning

confidence: 99%

Reactivity Control Method for Extended Burnup of Boiling Water Reactor Fuel Bundles

Aoyama¹,

Uchikawa²,

Takeda³

1989

Journal of Nuclear Science and Technology

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A reactivity control method was proposed for a boiling water reactor (BWR) fuel bundle, which has a potential for higher burnup with an increase in fuel enrichment. The new method optimized the distribution and amount of nonboiling water area in a fuel bundle in order to enhance the reactivity control capacity.Using the method, a 9x9 lattice fuel bundle with a small-sized channel box, large-sized water rods and a reduced fuel rod diameter was proposed for the discharged burnup of 70 GWd/t and the operational cycle length of 18 months. The core, which consists of the proposed fuel bundles with the bundle-averaged enrichment of 5.8)',;' and includes other modifications concerning a neutron low leakage loading pattern, natural uranium axial blankets, and spectral shift with recirculation flow control, has a cold shutdown margin greater than the design limit (15'~ dk) with minimum fuel bundle shuffling. Further, it has potentials for natural uranium savings of about 20)',;' per unit power and reduction in the amount of reprocessing of about 60)'~ per unit power, compared with current BWR designs.

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“…The former was realized by a new BWR core design concept<1l~<'l, which is a combination of fuel bundles with axial enrichment difference<'' and control cells<''. This core concept offers the simplified reactor operation<'l< 5 ' through no shallow control rod insertion and minimization of fuel bundle shuffling, control rod On the other hand, extending burnup with an increased fuel enrichment was effective for the latter approach<7H 9 '. Extending burn up also has a potential for reduction of fuel cycle cost by natural uranium savings and reduction in the amount of reprocessing of spent fuel per unit power.…”

Section: Introductionmentioning

confidence: 99%

Reactivity control method for extended burnup of boiling water reactor fuel bundles.

Aoyama

¹

,

Uchikawa

²

,

Takeda

³

1989

J. Nucl. Sci. Technol.

Self Cite

0

View full text Add to dashboard Cite

A reactivity control method was proposed for a boiling water reactor (BWR) fuel bundle, which has a potential for higher burnup with an increase in fuel enrichment. The new method optimized the distribution and amount of nonboiling water area in a fuel bundle in order to enhance the reactivity control capacity.Using the method, a 9x9 lattice fuel bundle with a small-sized channel box, large-sized water rods and a reduced fuel rod diameter was proposed for the discharged burnup of 70 GWd/t and the operational cycle length of 18 months. The core, which consists of the proposed fuel bundles with the bundle-averaged enrichment of 5.8)',;' and includes other modifications concerning a neutron low leakage loading pattern, natural uranium axial blankets, and spectral shift with recirculation flow control, has a cold shutdown margin greater than the design limit (15'~ dk) with minimum fuel bundle shuffling. Further, it has potentials for natural uranium savings of about 20)',;' per unit power and reduction in the amount of reprocessing of about 60)'~ per unit power, compared with current BWR designs.

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