Design study of advanced blanket for DEMO reactor US/JP Workshop on Fusion Power Plants and Related Advanced Technologies 23 th -24 th Feb. 2010 at UCSD,

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Presentation transcript:

Design study of advanced blanket for DEMO reactor US/JP Workshop on Fusion Power Plants and Related Advanced Technologies 23 th -24 th Feb at UCSD, U.S.A. JAEA Hiroyasu Utoh Outline Water-cooled LiPb BLK 2-D BLK analysis code He cooling system

Introduction PPCS (modelC) SlimCS 1 Solid breederLiquid breeder Water-cooled JA (TBM) ? He-cooledEU/JAEU/Kyoto Univ. To discuss DEMO reactor design widely, the comparing investigation of BLK options is important.

Blanket has “trade-off” problems 2 TBR Cooling Strength Breeder  Multiplier  Breeder  Multiplier  Coolant  Structural material  TBR > 1.05 Surface heat load Nuclear heating Disruption (EM) Coolant pressure First priority must be given to TBR because self-sufficient fuel supply is necessary in a fusion DEMO reactor. However, each BLK elements is a trade-off problem with TBR.

Solid breeder / Water-cooled ~SlimCS~ 3 Fusion power2.95 GW Surface heat load 1.0 MW/m 2 Neutron wall load Ave. 3 MW/m 2 (peak: 5 MW/m 2 ) Materials Structural: RAFM(F82H) Breeder: Li 4 SiO 4 Multiplier: Be / Be 12 Ti Coolant Sub-super critical water, 23 MPa T in / T out =290 / 360 ℃ K. Tobita, et al.: Nucl. Fusion 49 (2009) The RAFM steel is the most likely option for the blanket structural material. Considering the corrosion of F82H

Solid breeder / Water-cooled ~SlimCS~ 4 K. Tobita, et al.: Nucl. Fusion 49 (2009) SlimCS Net TBR>1.05 is difficult on high Pn The blanket structure is modeled 1-D and the nuclear heating and the temperature in the steady state are calculated by “ANIHEAT”. BLK coverage (~76%) BLK coverage (~76%) An optimized arrangement of the each material thickness is determined to satisfy the operating temperature

LiPb / Water-cooled ~SlimCS~ 5 Assumption for use in DEMO reactor ： Fusion power2.95 GW Surface heat load1.0 MW/m 2 Neutron wall load 3 MW/m 2 (peak: 5 MW/m 2 ) Coolant Sub-super critical water, 23 MPa T in / T out =290 / 360 ℃ Materials Structural: F82H Breeder: LiPb Same conditions as SlimCS Water-cooled / Solid breeder BLK FWBW&Header Plasma (neutron loading) LiPbCoolant Cooling is only water (not “dual-coolant”) Local TBR~1.2 (< Solid breeder)

LiPb with Be pebble / Water-cooled ~SlimCS~ 6 Assumption for use in DEMO reactor ： Coolant ： Sub-super critical water, 23 MPa, T in / T out =290 / 360 ℃ Multiplier ： Be pebble (Temp. limit ： 600 ℃ )  Design condition Structural mat. ： F82H (Temp. limit ： 550 ℃ ) Functional mat. (Temp. boundary) ： SiC/SiC Be pebble LiPb F82H Coolant 1000 ℃ 600 ℃ 550 ℃ 360 ℃ SiC/SiC Structural mat. (Pres. boundary) Functional mat. (Temp. boundary)

LiPb with Be pebble / Water-cooled ~SlimCS~ 7 SiC/SiC Be pebble F82H 450mm Neutron wall load ： P n =5MW/m 2 Double pipe structure:Boundary and cooling By using Be pebble, TBR is nearly equal to that of solid breeder on SlimCS. Issue (R&D): Processing method of SiC/SiC

Problem of BLK analysis 8 “ANIHEAT” can not simulate a model accurately. Blanket analysis method 2-D 1-D ANIHEAT 1-D neutron transport (ANISN) 1-D heat-transfer cal. + 1-D analysis with simpliﬁed models is efficient in ﬂexibly dealing with a trial and error process in the design of blanket concept.

2D-analysis code ~DOHEAT~ 9 DOHEATANIHEAT ANISN (1-D) 1-D + Neutron transport Neutron flux DOT3.5 (2-D) APPLE (1-D) Nuclear cal. Nuclear heating, TBR, etc Heat-transfer cal. Temperature + 2-D + APPLE (2-D) +

Analysis result sample by DOHEAT 10 Temperature distribution Nuclear heating distribution 2-D model ANIHEATDOHEAT Cal. time1~2 min.~30 min.  DOHEAT will be useful for the next step of BLK conceptual design

If we cool an uniform heating element equivalent to thermal power 2.4GW by some He-cooling pipe, How much is total pumping power for pressure loss? How much He-pumping power ? T in, v, p d0d0 Question ○Assumption He:T in /T out ＝ 300/380 ℃ p=8MPa L EU design Fusion power ： 2.385GW →Pumping power ： 194MW ○Approximation for pumping power Volume flow Specific heatCompressor efficiency(=0.85) Ratio of specific heat an uniform heating element equivalent to thermal power 2.4GW… 11 50W/cc Dual-coolant Case of single-coolant (He), how much is pumping power, GW class ?? T out, v’, p-  p

Evaluation result of He-pumping power (1) T in /T out ＝ 300/380 ℃, p=8MPa, d 0 =8mm Fusion power ： 2.4GW Electric power ： 0.88GW (efficiency: 0.37) 12 Net electric output per 1 cooling channel Because the removal heat is small Because the pressure loss is large

Evaluation result of He-pumping power (2) T in /T out ＝ 300/380 ℃, p=8MPa Heat removal ： medium Pressure loss ： small Packing factor ： large 13 Heat removal ： small Pressure loss ： small Packing factor ： large Heat removal ： medium Pressure loss ： large Packing factor ： small Heat removal ： large Pressure loss ： large Packing factor ： large Occupancy limit by pipe ( ＞ 75%) Packing factor  (TBR  )

Summary 14 The water-cooled LiPb+Be BLK has a potential for DEMO reactor The He-cooling system requires large pumping power. The key is heat removal vs. TBR But, it also has some R&Ds (SiC/SiC etc…) We deloped the “2-D nuclear thermal analysis code” DOHEAT DOHEAT will be useful for not only LiPb BLK but also “all” BLK analysis Future Plan Consideration of the effectiveness of LiPb flow (convection, MHD, etc) Detailed design for He-cooled BLK system