Overview of Helium Cooled Ceramic Reflector Test Blanket Module development in Korea

Cho, Seungyon; Ahn, Min Cheol; Lee, Jun Young; Park, Yi-Hyun; Lee, Eo Hwak; Yoon, Jae Sung; Kim, Tae Kyu; Lee, Cheol Woo; Yoon, Young Hoon; Kim, Suk Kwon; Jin, Hyung Gon; Shin, Kyong‐Oh; Jung, Yang‐Il; Jeong, Yong Hwan; Lee, Yong Ouk; Ku, Duck Young; Kim, Chang-Shuk; Park, Soon Chang; Yu, In-Keun; Jung, Ki-Jung

doi:10.1016/j.fusengdes.2013.05.072

Cited by 41 publications

(19 citation statements)

References 16 publications

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“…Lastly, a high effective Q-value is crucial to ensure an adequate EMF. The last two features, (n,xn) cross section and Q-value, contradict each other as (n,xn) reactions are endothermic, but overall the availability of extra neutrons upon (n,xn) reaction may compensate the loss of energy due to subsequent exothermic reaction with 6 Li and/or other alloy constituents. Additionally, the low absorption cross section also contradicts the high Q-value since heat is produced by absorption cross sections such as (n,␥).…”

Section: Preliminary Evaluationsmentioning

confidence: 99%

“…Studies in the past demonstrated the potential of LiPb as a coolant and breeder. However, the focus was usually on TBR and possible ways to maximize it such as by increasing the 6 Li enrichment [37]; (3) Pd, In, Au, and Ag feature a narrow acceptable range, but a relatively large EMF; (4) Ga, Cu, Sb and Zn are in the mid-range of acceptable lithium compositions with EMFs slightly higher than 1.1 but no greater than 1.2; (5) Sb, Pd and Au have very narrow acceptable ranges and limited EMF; (6) Na, Mg, Al, Ca, and Si never meet both constraints, mainly due to their detrimental effect on EMF. This results are in line with the observations made from the analysis on individual elements.…”

Section: Preliminary Evaluationsmentioning

confidence: 99%

“…The (n,t) cross section of 6 Li covers a wide range of energies as opposed to 7 Li, whose cross section only occurs in the high energy range; therefore, enriching the alloy in 6 Li increases neutron absorption in it and boosts TBR. LiSnZn was utilized for this enrichment sensitivity study.…”

Section: Lithium Enrichmentmentioning

confidence: 99%

“…The chosen composition (65% Li, 25% Sn, 10% Zn) meets all three sets of criteria described in the previous Section. 6 Li's concentration was increased from natural (7.5%) to 90% with increments of 5%. Fig.…”

Section: Lithium Enrichmentmentioning

confidence: 99%

“…The blanket is composed of the tritium breeding lithium ceramic pebbles and neutron multiplying beryllium pebbles. Similar concepts are being investigated in China, Korea, and India [5][6][7][8], while Japan is exploring a ceramic breeder cooled by pressurized water [9]. Other blanket designs utilize lead to lower chemical reactivity [10]; LiPb alone can serve as a breeder, coolant, neutron multiplier, and tritium carrier.…”

Section: Introductionmentioning

confidence: 99%

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Neutronics and activation analysis of lithium-based ternary alloys in IFE blankets

Jolodosky

Kramer

Meier

et al. 2016

Fusion Engineering and Design

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h i g h l i g h t s • Monte Carlo calculations were performed on numerous lithium ternary alloys. • Elements with high neutron multiplication performed well with low absorbers. • Enriching lithium decreases minimum lithium concentration of alloys by 60% or more. • Alloys that performed well neutronically were selected for activation calculations. • Alloys activated, except LiBaBi, do not pose major environmental or safety concerns. a b s t r a c t An attractive feature of using liquid lithium as the breeder and coolant in fusion blankets is that it has very high tritium solubility and results in very low levels of tritium permeation throughout the facility infrastructure. However, lithium metal vigorously reacts with air and water and presents plant safety concerns. The Lawrence Livermore National Laboratory is carrying an effort to develop a lithium-based ternary alloy that maintains the beneficial properties of lithium (e.g. high tritium breeding and solubility) and at the same time reduces overall flammability concerns. This study evaluates the neutronics performance of lithium-based alloys in the blanket of an inertial fusion energy chamber in order to inform such development. 3-D Monte Carlo calculations were performed to evaluate two main neutronics performance parameters for the blanket: tritium breeding ratio (TBR), and the fusion energy multiplication factor (EMF). It was found that elements that exhibit low absorption cross sections and higher q-values such as Pb, Sn, and Sr, perform well with those that have high neutron multiplication such as Pb and Bi. These elements meet TBR constrains ranging from 1.02 to 1.1. However, most alloys do not reach EMFs greater than 1.15. Additionally, it was found that enriching lithium with 6 Li significantly increases the TBR and decreases the minimum lithium concentration by more than 60%. The amount of enrichment depends on how much total lithium is in the alloy to begin with. Alloys that performed well in the TBR and EMF calculations were considered for activation analysis. Activation simulations were executed with 50 years of irradiation and 300 years of cooling. It was discovered that bismuth is a poor choice due to achieving the highest decay heat, contact dose rates, and accident doses. In addition, it does not meet the waste disposal ratings (WDR). Some of the activation results for alloys with Sn, Zn, and Ga were in the higher end and should be considered secondary to elements such as Sr and Ba that had overall better results. The results of this study along with other considerations such as thermodynamics, and chemical reactivity will help down select a preferred lithium ternary alloy.

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Section: Preliminary Evaluationsmentioning

confidence: 99%

Section: Preliminary Evaluationsmentioning

confidence: 99%

Section: Lithium Enrichmentmentioning

confidence: 99%

Section: Lithium Enrichmentmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Neutronics and activation analysis of lithium-based ternary alloys in IFE blankets

Jolodosky

Kramer

Meier

et al. 2016

Fusion Engineering and Design

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Helium cooled dual breeder blanket–preliminary design analyses of a candidate breeding blanket concept for near term IndianDEMOfusion reactor

et al. 2020

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Summary Helium cooled dual breeder (HCDB) blanket concept is designed for Indian DEMO fusion reactor and it is made of two tritium breeder materials PbLi and Li2TiO3. It has helium as a coolant and the India specific RAFMS as a structural material. High‐pressure helium first cools the plasma facing first‐wall and after that, it will extract heat from PbLi and ceramic breeder. Since PbLi is not used as a coolant, it therefore circulates with a low flow rate. It will overcome the corrosion and MHD issues associated with high temperature and high flow rate of PbLi. The idea behind the concept is to make a design which can be made using the existing blanket materials, extract high‐grade heat from the reactor and also enhance the availability. In HCDB blanket the role of neutron multiplier is done by PbLi, an alternative to the beryllium and it eliminates the issue associated with high toxic beryllium handling. It can be a potential tritium breeding blanket concept along with lead lithium cooled ceramic breeder (LLCB) and helium cooled ceramic breeder (HCCB) for near term Indian demonstration nuclear fusion power plant. In order to realize the HCDB conceptual design, preliminary estimations of tritium production, nuclear heat density have been carried out. The thermal behaviors of the HCDB blanket in Indian DEMO conditions have been also assessed and reported here. The assessment establishes the proof of HCDB blanket concept and supports it to be a good alternate blanket candidate for the Indian DEMO. The paper describes the HCDB concept along with analysis to verify the tritium self‐sufficiency and materials temperature limits.

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The investigation of various type irradiation effects on aluminum nitride ceramic

Dukenbayev

Kozlovskiy

Alyamova

et al. 2019

J Mater Sci: Mater Electron

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Overview of Helium Cooled Ceramic Reflector Test Blanket Module development in Korea

Cited by 41 publications

References 16 publications

Neutronics and activation analysis of lithium-based ternary alloys in IFE blankets

Neutronics and activation analysis of lithium-based ternary alloys in IFE blankets

Helium cooled dual breeder blanket–preliminary design analyses of a candidate breeding blanket concept for near term IndianDEMOfusion reactor

The investigation of various type irradiation effects on aluminum nitride ceramic

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