Whole-core depletion studies in support of fuel specification for the nextgeneration nuclear plant (NGNP) core.

Kim, T. K.; Yang, Won Sik; Taiwo, T. A.; Khalil, Hassan A.

doi:10.2172/895674

Cited by 11 publications

(16 citation statements)

References 4 publications

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“…The cycle lengths obtained for the single-batch cases are plotted in Figure 5. The overall trends of the LS-VHTR are similar to those for the helium-cooled VHTR [11]; the cycle length increases with uranium enrichment and packing fraction, and the optimum packing fraction was observed around 25% (see Figure 5). Additionally, the discharge burnup …”

Section: Discharge Burnup and Required Uranium Enrichmentsupporting

confidence: 56%

“…The required enrichment is smallest for the onebatch case, but its discharge burnup is smaller than the target value. Therefore, the two-batch scheme is desirable to satisfy simultaneously the target cycle length and discharge burnup and the constraint on the fuel enrichment (similar conclusion was obtained in the helium-cooled VHTR study [11]). …”

Section: Figure 5 Cycle Length As Function Of Packing Fraction and Umentioning

confidence: 53%

“…Thus, in subsequent parametric studies, the fuel cycle length and discharge burnup were evaluated using the WIMS8 lattice code and a 1.5% neutron leakage approximation; the assembly k inf must be 1.015 at the critical burnup point. For the helium-cooled VHTR, a value of about 3 ~ 4 %Δk was found appropriate [11]. Note that the neutron leakage from the LS-VHTR core is lower because it uses a solid cylindrical core and its size is bigger than that of the helium-cooled VHTR core.…”

Section: Estimation Of Core Reactivity and Cycle Lengthmentioning

confidence: 94%

“…Each fuel element is explicitly modeled as a burn-zone; there are 2,560 burn zones with 256 radial and 10 axial zones. A simplified lumped fission products (LFP) model, which was developed for previous helium-cooled VHTR core analysis [11] was used in order to save computation time. and fuel element (assembly).…”

Section: Estimation Of Core Reactivity and Cycle Lengthmentioning

confidence: 99%

“…[11] The linear reactivity model developed and discussed in Section 3.1 was used for the study. In this study, the reactor capacity factor and Li-enrichment were assumed to be 90% and 99.995%, respectively.…”

Section: Discharge Burnup and Required Uranium Enrichmentmentioning

confidence: 99%

See 4 more Smart Citations

Preliminary neutronic studies for the liquid-salt-cooled very hightemperature reactor (LS-VHTR).

Kim¹,

Taiwo²,

Yang³

2005

Self Cite

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Section: Discharge Burnup and Required Uranium Enrichmentsupporting

confidence: 56%

Section: Figure 5 Cycle Length As Function Of Packing Fraction and Umentioning

confidence: 53%

Section: Estimation Of Core Reactivity and Cycle Lengthmentioning

confidence: 94%

Section: Estimation Of Core Reactivity and Cycle Lengthmentioning

confidence: 99%

Section: Discharge Burnup and Required Uranium Enrichmentmentioning

confidence: 99%

See 3 more Smart Citations

Preliminary neutronic studies for the liquid-salt-cooled very hightemperature reactor (LS-VHTR).

Kim¹,

Taiwo²,

Yang³

2005

Self Cite

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Comparison of homogeneous and heterogeneous thorium fuel blocks with four drivers in advanced high temperature reactors

et al. 2020

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Thorium is an attractive potential fuel owing to its abundance and unique thermal, neutronic, and chemical properties. One way to utilize thorium in block-type advanced high temperature reactors (AHTRs) is to homogenously mix the driver fuel (eg, U-233) with thorium in every fuel kernel of the tristructural-isotropic particles in a fuel block, which is the mixed oxide fuel (MOX) concept. Application of the seed and blanket (S&B) concept, that is, driver fuel in the seed region of a fuel block and thorium in the blanket region, is also another method to utilize thorium. To investigate the differences in the utilization of thorium using the MOX and S&B concepts in AHTRs, their multiplication factors (k ∞ ), discharge burnups, conversion ratios, and reactivity temperature coefficients are compared. The investigated drivers include U-233 (U3), weapons-grade uranium (WU), weapons-grade plutonium (WPu), and reactor-grade plutonium (RPu). The results demonstrate that the MOX block with plutonium drivers has a higher discharge burnup in comparison with the S&B block. When the heavy metal mass is 6 kg and the initial mass of the fissile materials is 0.65 kg per block, the MOX block achieves 27% higher discharge burnup than the S&B block with the RPu driver. In contrast, the S&B block achieves higher discharge burnup in the case of uranium drivers (U3 and WU). The MOX block achieves a higher conversion ratio for all the drivers. Furthermore, the MOX block achieves a stronger negative moderator temperature coefficient of reactivity than the S&B block for all the driver fuels.

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Reactor and Laser Coupling

Prelas

2016

Nuclear-Pumped Lasers

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This chapter discusses the design of how nuclear reactors are coupled to lasers. The design is complex in that there are many ways to interface the reactor, which serves as a neutron source, to the laser medium. There are issues with the fuel interface to the laser that includes the phase, the type of fuel, how the fuel is put into proximity to the laser medium and the potential chemical interactions of the fuel with the laser medium. The coupling of the optics to the laser medium is also an important consideration and how radiation damage may impact the optical components, structural materials and subsystems. There are also cooling and control issues as well.

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Whole-core depletion studies in support of fuel specification for the nextgeneration nuclear plant (NGNP) core.

Cited by 11 publications

References 4 publications

Preliminary neutronic studies for the liquid-salt-cooled very hightemperature reactor (LS-VHTR).

Preliminary neutronic studies for the liquid-salt-cooled very hightemperature reactor (LS-VHTR).

Comparison of homogeneous and heterogeneous thorium fuel blocks with four drivers in advanced high temperature reactors

Reactor and Laser Coupling

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