Reactor core and actinide production evaluation based on different loading material of recyled spent nuclear fuel of LWR in FBR

Permana, Sidik; Saputra, Geby; Suzuki, Masahiro; Su’ud, Zaki; Saito, Masaki

doi:10.1016/j.ijhydene.2016.01.102

Cited by 13 publications

(10 citation statements)

References 17 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…A great number of works have been done for the utilization of nuclear waste transuranium and fertile material in fast reactors. [27][28][29][30][31] The transformation of actinide isotopes is analyzed in detail. 31 In that respect, the performance of fusion-fission (hybrid) reactors for the utilization of nuclear waste of LWR and CANDU reactors as well as that of fertile has been outlined in a high number of studies.…”

Section: Discussionmentioning

confidence: 99%

“…[27][28][29][30][31] The transformation of actinide isotopes is analyzed in detail. 31 In that respect, the performance of fusion-fission (hybrid) reactors for the utilization of nuclear waste of LWR and CANDU reactors as well as that of fertile has been outlined in a high number of studies. 26,[32][33][34][35][36] ADSs have also great potential to burn MA in the waste of conventional reactors as well as fertile materials, such as thorium and 238 U.…”

Section: Discussionmentioning

confidence: 99%

“…Fast reactors are available and mature technology. A great number of works have been done for the utilization of nuclear waste transuranium and fertile material in fast reactors . The transformation of actinide isotopes is analyzed in detail …”

Section: Introductionmentioning

confidence: 99%

See 2 more Smart Citations

Large-scale energy production with thorium in a typical heavy-water reactor using high-grade plutonium as driver fuel

Şahi̇n

Şarer²

2018

Int J Energy Res

View full text Add to dashboard Cite

Summary Thorium can be introduced into the energy vector in combination with high‐grade plutonium (HG‐Pu). Excellent neutron economy of heavy‐water moderator allows use of mixed ThO2/HG‐PuO2 fuel in heavy‐water reactors with high efficiency, leading to the exploitation of large world thorium reserves and extending the availability of the nuclear energy by two orders of magnitude. In the present work, the criticality calculations have been performed with the code MCNPX 3‐D geometrical modeling of a typical heavy‐water reactor, where the structure of all fuel rods and bundles is represented individually. In the course of time calculations, nuclear transformation and radioactive decay of all actinide elements as well as fission products are considered. Five different fuel compositions have been selected for investigations: (1) 97% thoria (ThO2) + 3% PuO2; (2) 96% ThO2 + 4% PuO2; (3) 95% ThO2 + 5% PuO2; (4) 94% ThO2 + 6% PuO2; and (5) 92% ThO2 + 8% PuO2. The behavior of the criticality k∞ and the burn‐up values of the reactor have been pursued by full power operation at 640 MWel (2180 MWth) for approximately 7 years. Time calculations have been conducted with MCNPX and CINDER codes under consideration of all nuclear transformation and radioactive decay processes on the actinide isotopes and fission fragments. As the reactor allows fuel recharging at on‐power operation mode, the reactor criticality has been followed down to keff,end = ~1.05. The corresponding burn‐up values and operation periods for the investigated modes are (1) 18 GWd/MT and 780 days; (2) 27 GWd/MT and 1200 days; (3) 35 GWd/MT and 1560 days; (4) 44 GWd/MT and 1940 days; and (5) 60 GWd/MT and 2640 days. Among the investigated four modes, 94% ThO2 + 6% PuO2 seems a reasonable choice under consideration of the high price of the HG‐Pu as driver fuel. The mixed fuel has the potential of an extensive exploitation of thorium resources. Reactor will run with the same fuel charge for approximately 5 years and allow a fuel burn‐up approximately 44 GWd/MT, comparable with conventional light‐water reactors (LWRs). Plutonium component of the mixed fuel will become nonprolific after few months of plant operation through the accumulation of even isotopes. Addition of few percent natural uranium to the initial mixed fuel charge will keep the 233U component below 22% and hence at nonprolific level over the entire plant operation period. Replacement of 4% ThO2 with 4% nat‐UO2 will practically not change main technical parameters of the reactor.

show abstract

Section: Discussionmentioning

confidence: 99%

Section: Discussionmentioning

confidence: 99%

See 1 more Smart Citation

Large-scale energy production with thorium in a typical heavy-water reactor using high-grade plutonium as driver fuel

Şahi̇n

Şarer²

2018

Int J Energy Res

View full text Add to dashboard Cite

show abstract

“…A large reactor core was adopted because it could easily obtain criticality 6 . A pancake core could decrease the load of severe heat flow in the axial direction and enhanced the result 7,8 . Nitride fuel ( 15 N) as the fuel could increase the k‐eff and reduce the production of 14 C due to 14 N (n,p) 14 C reaction 9‐11 .…”

Section: Methodsmentioning

confidence: 99%

Initial core design analysis of lead (208) ‐bismuth eutectic‐cooled reactor with radial fuel shuffling

et al. 2021

Self Cite

View full text Add to dashboard Cite

Summary Natural uranium is utilized in a small percentage by the Light Water Reactor (LWR) and also by the once‐through Fast Breeder Reactor. One of the reactor designs that can increase the natural uranium utilization is the MCANDLE (Modified Constant Axial shape of Neutron flux, nuclides densities, and power shape During Life of Energy production) reactor. The scheme divides the core into several discrete regions. The modified CANDLE reactor will only need natural uranium as fuel input after reaching quasi‐equilibrium conditions. In this study, We used a core with certain Plutonium (Pu) composition in each region as a startup core. Initially, the Pu content in each region imitates that of the reactor core at the quasi‐equilibrium state. We calculated the neutronics of the initial core by the SRAC that stands for Standard Reactor Analysis Code System and used JENDL 4.0 as a nuclear data library. Plutonium (Pu) from LWR spent fuel was utilized as the initial reactor fuel. However, excess reactivity is more than 10%. It is because there are no other fission products. Therefore, we replace other fission products with a reduction in the volume of fuel cells. The volume reduction was adjusted to the level of burnup in each region at the quasi‐equilibrium condition. Hence, there are differences in the volume reduction ratio for each fuel cell. The method can reduce excess reactivity to 5%. The reduction of the volume of fuel cells can also reduce the amount of plutonium as the initial fuel for the reactor core. Also, the spent fuel burnup is 48% FIMA. The design could increase the utilization of natural uranium without an enrichment process.

show abstract

“…At the same time, it gives a negative void reactivity coefficient and provides some other advantages such as high burnup and more proliferation resistance compared with fissile plutonium as a basis of uranium–plutonium cycle case. More proliferation resistance and more breeding capability of thorium fuel can be compared with the reactor, which shows plutonium isotopes in plutonium cycle scheme and gives some advantages for fuel breeding capability as well as some plutonium compositions, which obtain more proliferation resistance . The objective of the study is to analyze the design optimization of heavy water cooled breeding reactors using 233 U–Th as fuel based on the safety aspect of void reactivity and fuel conversion condition of the reactor by adopting a nuclear equilibrium state model .…”

Section: Introductionmentioning

confidence: 99%

Void reactivity aspect and fuel conversion potential of heavy water cooled thorium reactor

et al. 2016

Self Cite

View full text Add to dashboard Cite

Summary Design study on heavy water cooled thorium breeding reactor has been investigated by adopting a nuclear equilibrium state model. Conversion ratio, as an important index, has been evaluated to estimate the breeding capability of the reactors. Void reactivity coefficient has also been investigated to evaluate performance index of safety aspect, which is based on the criticality performance of the reactors during voided condition. In addition, moderator‐to‐fuel ratio has also been employed to analyze its effect to the required enrichment, conversion ratio, and void reactivity coefficient as well as different burnups and fuel pin diameter effects. Void reactivity coefficient indicates a criticality condition of the reactor when some coolants are lost. If the negative value of void reactivity is achieved, it means that the reactor has less reactivity condition as well as less power production when lost of coolant occurred. Higher fuel conversion capability, that more nuclear fuel are produced, those additional fuel productions can be used for next operation or for other reactors. The results show that higher fuel conversion ratio can be achieved for less moderator‐to‐fuel ratio because of the harder neutron spectrum effect, while it requires more fissile content of 233U to maintain the reactor operation from fission reaction. Higher burnup gives less conversion ratio because some fissile materials are used to maintain longer reactor operation, and at the same time, it requires more initial required fissile 233U for higher burnup. In addition, it requires less fissile 233U for thicker fuel pin diameter, while its conversion ratio becomes higher, and void reactivity coefficient is more negative for thicker fuel pin diameter. The results also show that thorium utilization on heavy water cooled reactor gives all negative void reactivity values, which means that the system has a safety condition in terms of void reactivity condition. At the same time, it shows some feasible conditions for obtaining fuel breeding to increase the sustainability of nuclear fuel. Copyright © 2016 John Wiley & Sons, Ltd.

show abstract

Reactor core and actinide production evaluation based on different loading material of recyled spent nuclear fuel of LWR in FBR

Cited by 13 publications

References 17 publications

Large-scale energy production with thorium in a typical heavy-water reactor using high-grade plutonium as driver fuel

Large-scale energy production with thorium in a typical heavy-water reactor using high-grade plutonium as driver fuel

Initial core design analysis of lead (208) ‐bismuth eutectic‐cooled reactor with radial fuel shuffling

Void reactivity aspect and fuel conversion potential of heavy water cooled thorium reactor

Contact Info

Product

Resources

About