ABWR-II Core Design with Spectral Shift Rods for Operation with All Control Rods Withdrawn

Moriwaki, Masanao; Aoyama, Motoo; Anegawa, Takafumi; Okada, Hiroyuki; Sakurada, Koichi; Tanabe, Akira

doi:10.13182/nt04-a3474

Cited by 6 publications

(2 citation statements)

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“…In the 21st century, the spectral-shift effect research was applied in the new-type advanced reactor. In the ABWR-II core design, spectral-shift rods were adopted and analyzed (Anegawa et al, 2001;Moriwaki et al, 2004). Results show that the average discharge burnup was improved by 5% and uranium weight was saved by 6∼7%.…”

Section: Introductionmentioning

confidence: 99%

Application of the Spectral-Shift Effect in the Small Lead-Based Reactor SLBR-50

et al. 2021

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In the design of a nuclear reactor, improving fuel utilization and extending burnup are two of the most important goals. A concept design of spectral-shift control rods is presented to extend cycle length and fuel utilization. First, a small lead-based reactor, SLBR-50, is preliminarily designed, and the design rationality is proved. Next, the concept design of spectral-shift control rods is presented and analyzed. Finally, numerical results of the small reactor design show that the burnup depth is extended by 73.3% and the fuel utilization rate for 235U and 238U is improved by 66.6 and 68.4%. All results are calculated using a Monte-Carlo code RMC. These results show advantages of the concept design for the spectral-shift control rod.

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Section: Introductionmentioning

confidence: 99%

Application of the Spectral-Shift Effect in the Small Lead-Based Reactor SLBR-50

et al. 2021

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“…These detailed pin-wise calculations can be effectively utilized in the development of next generation nuclear reactors. 3,4) This is partially because heterogeneities inside the lattices tend to be higher in these reactor cores and their influences on neighboring lattices may not be negligible. In addition, costly experiments, which will possibly be required for verification of any newly developed design, could be replaced by the detailed pin-wise analyses, thus contributing to the overall cost reduction of reactor development.…”

Section: Introductionmentioning

confidence: 99%

Multi-Assembly Analysis with an Advanced Correlated Sampling Method

Moriwaki

2003

Journal of Nuclear Science and Technology

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The Advanced Correlated Sampling (ACS) method, which can greatly enhance the calculation efficiency of Monte Carlo (MC) methods using a perturbation technique and a pseudo-scattering technique, is improved so as to be able to handle multi-assembly analysis. Two boundary connection methods-the neutron path connection and neutron current connection methods-are developed, and their accuracies for a 2×2 multi-assembly system are confirmed. The speedup factor against the corresponding direct MC calculation is a maximum of about 100. These boundary connection methods are also applied in pin-wise 2-D quarter core calculations as an example of a large-scale system. A newly developed perturbed neutron source iteration technique allows for very smooth source convergence. Furthermore, by incorporating the Direct Response Matrix (DRM) method as the acceleration means for the source convergence, the number of source iteration cycles is significantly shortened. The results confirm that this improved ACS method has the ability to perform pin-wise whole core calculations very accurately and efficiently.

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Plutonium isotopic composition of high burnup spent fuel discharged from light water reactors

Nakano¹,

Ōkubo²

2011

Annals of Nuclear Energy

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ABWR-II Core Design with Spectral Shift Rods for Operation with All Control Rods Withdrawn

Cited by 6 publications

References 1 publication

Application of the Spectral-Shift Effect in the Small Lead-Based Reactor SLBR-50

Application of the Spectral-Shift Effect in the Small Lead-Based Reactor SLBR-50

Multi-Assembly Analysis with an Advanced Correlated Sampling Method

Plutonium isotopic composition of high burnup spent fuel discharged from light water reactors

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