Feasibility study on AFR-100 fuel conversion from uranium-based fuel to thorium-based fuel

Heidet, Florent; Kim, T.; Grandy, C.

doi:10.2172/1047454

Cited by 2 publications

(4 citation statements)

References 11 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…There are two types of control assemblies. The first type is a primary control assembly that is used for reactivity control during operation with natural boron as an absorber material, and the second type is a secondary control assembly that is composed of 90% enriched 10 B for reactor shutdown. Figure 2 shows the radial layout of the reactor core.…”

Section: Core Designmentioning

confidence: 99%

“…TerraPower Inc. proposed the traveling wave reactor that aimed at an ultra-long-life core by allowing fuel shuffling every 18 to 24 months [8]. An advanced SFR with a power rate of 100 MWe (AFR-100) was developed, targeting a small electrical grid with a long operation time without refueling [10]. An advanced SFR with a power rate of 100 MWe (AFR-100) was developed, targeting a small electrical grid with a long operation time without refueling [10].…”

Section: Introductionmentioning

confidence: 99%

“…The SFR is one of the Generation IV reactor concepts [1][2][3][4][5]. Many SFR concepts have been proposed to achieve a long-life core by adopting a fast spectrum [6][7][8][9][10]. Tak et al proposed the 2600 MW ultra-long cycle fast reactor (UCFR-1000) for a 60-year operation without refueling and adopting the breed-andburn (B&B) strategy [6].…”

Section: Introductionmentioning

confidence: 99%

“…A conceptual design of a super-safe, small, and simple (4S) reactor was proposed by Toshiba Corp. and CRIEPI to meet design criteria such as negative temperature feedback reactivity coefficients including sodium void worth and a core lifetime longer than 10 years [9]. An advanced SFR with a power rate of 100 MWe (AFR-100) was developed, targeting a small electrical grid with a long operation time without refueling [10]. On the other hand, the SMR concept provides flexibility in design, siting, and the fuel cycle option, and it can be transported from the prelicensed factories to the remote plant sites [11][12][13].…”

Section: Introductionmentioning

confidence: 99%

See 3 more Smart Citations

Design study of long-life small modular sodium-cooled fast reactor

Park

Tak

Kim

et al. 2016

Int. J. Energy Res.

View full text Add to dashboard Cite

Summary This paper presents a new design for a small modular sodium‐cooled fast reactor core with an optimized lifetime and reactivity swing through the analysis of various breed‐and‐burn strategies and its neutronic analyses in terms of active core movements, isotopic mass balance, kinetic parameters, and inherent safety. The new core design aims at a power level of 260 MW with a long lifetime of 30 years without refueling and a reactivity swing smaller than 1000 pcm. Starting from five initial candidate cores with various breed‐and‐burn strategies, an optimum core was selected from a combination of the two candidates that shows a proper breeding behavior with the optimized uranium enrichment in the low‐enriched uranium region and the optimized size of the blanket region. The depletion analysis of the new core provides various reactor design parameters such as the core multiplication factor, breeding ratio, heavy metal mass change, power distribution, and summary of neutron balance. In addition, the perturbation analysis provides the reactor kinetic parameters and reactivity feedback coefficients for the inherent safety analysis of the core. The integral reactivity parameters of the quasi‐static reactivity balance analysis demonstrate that the new core is inherently safe in cases of unprotected loss of flow, unprotected loss of heat sink, and unprotected transient over power. Copyright © 2016 John Wiley & Sons, Ltd.

show abstract

Section: Core Designmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

See 2 more Smart Citations

Design study of long-life small modular sodium-cooled fast reactor

Park

Tak

Kim

et al. 2016

Int. J. Energy Res.

View full text Add to dashboard Cite

show abstract

Feasibility study on ultralong-cycle operation and material performance for compact liquid metal-cooled fast reactors: a review work

Tak

Choe

Jeong

et al. 2015

Int. J. Energy Res.

View full text Add to dashboard Cite

SUMMARYThis paper reviews the feasibility of ultralong-cycle operation on a compact liquid metal-cooled fast reactor (LMR) firstly by assessing the operation of a long-life fast reactor core and secondly by evaluating material performance in respect to both long-cycle operation and compact-size fast reactor. Many kinds of reactor concepts have been proposed, and LMR and small modular reactor (SMR) are the issued leading technologies for generation four (Gen-IV) reactor system development. The breed-and-burn strategy was proposed as a core burning strategy to operate a long cycle, and it has been evaluated in this paper with two reactor concepts: constant axial shape of neutron flux, nuclide densities, and power shape during life of energy and ultralong cycle fast reactor. In addition, Super-Safe, Small, and Simple and small modular fast reactor, compact LMR concepts, have been simulated to evaluate their long-life operation strategies. For the other practical issues, the materials for fuel, coolant, and structure have been identified and some of them are selected to have their performance optimized specifically for compact LMR with a long-cycle operation. It is believed that this comprehensive review will propose a proper direction for future reactor development and will be followed by the next step research for a complete reactor model with the other reactor components.

show abstract

Feasibility study on AFR-100 fuel conversion from uranium-based fuel to thorium-based fuel

Abstract: Executive summaryThe feasibility study of converting a fast reactor from uranium-based fuel to thorium-based fuel was studied using the 100 MW e

Cited by 2 publications

References 11 publications

Design study of long-life small modular sodium-cooled fast reactor

Design study of long-life small modular sodium-cooled fast reactor

Feasibility study on ultralong-cycle operation and material performance for compact liquid metal-cooled fast reactors: a review work

Contact Info

Product

Resources

About