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Frontiers in Energy

ISSN 2095-1701

ISSN 2095-1698(Online)

CN 11-6017/TK

Postal Subscription Code 80-972

2018 Impact Factor: 1.701

Front Energ    0, Vol. Issue () : 349-357    https://doi.org/10.1007/s11708-011-0168-4
FEATURE ARTICLE
A perspective of “Nuclear Hot Spring” for long-term sustainable economy of the world
Yingzhong LU()
Green Hi-Tek, 104 Harland Court, Oak Ridge, TN 37830, USA
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Abstract

The rapid growth of human economy in the late 20th century gave rise to great concern over sustainability of the world. A pessimistic “Full World Model” forecasts that human economy could not develop further. The nuclear fission (and fusion later), however, could release huge amount of energy to create sufficient useful material resources and turn the said pessimistic modelinto a new optimistic “Sustainable World Model”.The dilemma of nuclear energy (Military Giant vs. Civil Dwarf) jeopardizes its performance as a “Technologic Fixer”. According to Mother Nature’s teachings, the elimination of the root-causes of the design-based risk factors could solve this problem. Recent technology break-through from inherent safety to natural safety has been made in China. The proposed full-power natural circulation “Nuclear Hot Spring (NHS)” reactor could operate solely on natural forces without complex man-made coolant circulation equipment and human-operated control systems. The cheap, unlimited supply of energy from nuclear energy could change the geopolitics forever, and finally eliminate the root-causes of most international and regional conflicts.

Keywords natural safety reactor      full power natural circulation      sustainable world economy     
Corresponding Author(s): LU Yingzhong,Email:yingzhonglu@yahoo.com   
Issue Date: 05 December 2011
 Cite this article:   
Yingzhong LU. A perspective of “Nuclear Hot Spring” for long-term sustainable economy of the world[J]. Front Energ, 0, (): 349-357.
 URL:  
https://academic.hep.com.cn/fie/EN/10.1007/s11708-011-0168-4
https://academic.hep.com.cn/fie/EN/Y0/V/I/349
Fig.1  Daly’s model
Fig.2  Sustainable world model
Fig.3  End of “First Nuclear Era”
Fig.4  Track on “Inherently Safe Nuclear Power”
Fig.5  Decreasing design risk factors
No.Risk factorRoot causesRemedies
1Fuel meltingMetal clad & low MP fuelCeramic clad & high MP fuel
2LOCA/LOFCAHigh pressure, low BP coolant; forced circulationLow P, H BP cool; natural circulation
3Anticipated transient without scram (ATWS)Large excess reactivity (k); solid control rods syst.Keep minim. excess k; fluid control syst.
4Human failuresHuman intervention on critical safety issuesMitigate human intervention
Tab.1  Typical design-based risk factors
Fig.6  Pre-history natural reactors
Fig.7  Isotope signatures for natural nuclear reactors
ItemData
U-235 enrichment/%~ 3
Critical period/min~ 30
Shut-down/cooling/min~ 90
Total operating time/MRY~ 2.4
No. of restarting>7 billion
Total energy generated/ (GW·a)15
Average power level/(kW·t)~ 100
Human interventionNone
Tab.2  Major data of the Oklo natural nuclear reactors
Fig.8  Conceptual design of PB-AHTR
Reactor typeReactor power/MWeReactor & Auxi. Vol./(m3·(MWe)-1)Turbine Bldg. Vol./(m3·(MWe)-1)Ancillary structures Vol./(m3·(MWe)-1)Total Bldg. Vol./(m3·(MWe)-1)
1970’s PWR100012916146336
ABWR138021125223486
ESBWR1550+132+16645343
EPR160022810787422
GT-MHR286388024412
PBMR170101502701285
Mod. PB-AHTR41010511540260
Tab.3  Comparison of construction values of different types of NPPs
Fig.9  1—Fuel balls; 2—Fertile balls; 3—Central channel; 4—Diffuser; 5—Riser; 6—Down-comer; 7—Ball feed; 8—Ball discharge; 9—Enlarged View; 10—Balls; 11—HX; 12—1stchannel; 13,14—2nd coolant in/out; 15—Pool vessel; 16—Insulation; 17—Reactor pit; 18—Control balls channel
True naturally-safe reactor NHS
Fig.10  1—1st coolant channel; 2—1st channel finned area; 3—2nd coolant channel; 4—2nd channel finned area; 5—Division plate; 6,7—Upper & lower sealing bars; 8—Upper diffuser; 9—Diffuser fins; 10—2nd outlet pipe; 11—Lower diffuser; 12—2nd inlet pipe; 13–15—Side plates
Ultra-low resistance HX
Reactor power/(GW·t)Core size*/mCore ?P/(kg·m-2)HX ?P/(kg·m-2)Center hole ?P/(kg·m-2)Riser ?P/(kg·m-2)Downcomer ?P/(kg·m-2)Total ?P/(kg·m-2)Riser height/mTot. drive force/(kg·m-2)Max Fuel TC/ oC
0.1-0.63.2/1.2×41110010.10.11172.01831055
0.5-3.05/1.6×102810050.10.11343.02741057
2.5-156.4/2×12308158490.20.6523109161157
10-608.5/3×247421581611.02.611182018321154
Tab.4  Simulation results of four series of NHS (No. of modules, 1-6) (Basic data: fuel ball =0.03 m; coolant =800°C, =1000°C)
Fig.11  1a,1b,1c-Core modules; 2-Fuel balls 3-Fertile balls; 4-Ball loading; 5-Ball discharge; 6-Down-comer; 7-Center hole; 8-Diffuser; 9-Riser; 10-HX; 11-2nd loop; 12-Coolant pool; 13- Insulation; 14-Protection shell; 15-Underground pit
NHS reactor consisting of multiple core-modules
Fig.12  
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