IMPROVED BWR CORE DESIGN USING HYDRIDE FUEL
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1 Joint Reactor Seminar University of Tokyo (GoNERI) and UC Berkeley March 5, 2009 IMPROVED BWR CORE DESIGN USING HYDRIDE FUEL Massimiliano Fratoni, Alessandro Piazza, Ehud Greenspan University of California, Berkeley Paolo Ferroni, Neil Todreas Massachusetts Institute of Technology
2 OUTLINE Work motivation Hydride fuel BWR core designs Analysis methodology Hydride fuel BWRs performance Neutronic analysis Thermo-hydraulic analysis Stability analysis 2
3 OXIDE FUEL BWR CORE IS HIGHLY HETEROGENEOUS Two phase moderator Reference model GE11 BWR/5 9x9 Need for extra moderation Water rods Partial length fuel rods E6 Water gaps in between bundles High level of heterogeneity Axial and radial enrichment distribution E1 E2/E3 E4/E5 E5/E6 Partial E5 Partial E6 Fuel rods enrichment levels E1<E2< <E6 Gd E4 3
4 HYDRIDE FUEL FOR BWRS Hydride fuel examined U(45w/o)-ZrH1.6 High hydrogen density similar to liquid water at 0.7 g/cm 3 High thermal conductivity about 5 times that of UO 2 Low fission gas release But relatively large swelling use LM bonding Incentives for using hydride fuel in BWR No need for the extra moderation Eliminate water rods and partial length rods to insert fuel rods Minimize thickness of water gaps for larger bundles Reduce heterogeneity of BWR core Reduce number of enrichments per bundle 4
5 HYDRIDE FUEL BUNDLE DESIGN FOR UPPER BOUND ANALYSIS Upper bound estimate on improvement possibilities are obtained by examining a design that is not practical to implement in existing BWR designs Same core volume per bundle as oxide fuel Same OD as in oxide fuel 10x10 array 5% enrichment uniform Dispersed control rods Optimal P/D to maximize BU from 1-D analysis 5
6 FUEL BUNDLE DESIGNS COMPATIBLE WITH THE CURRENT BWR CORE LAYOUT Corner cruciform control rods CCCR 2 cruciform corner control rods 1 square corner position for instrumentations 93 full length fuel rods Control blades CB 1 control blade every 4 bundles Reduced canisters distance 100 full length fuel rods 6
7 NEUTRONIC AND THERMAL-HYDRAULIC ANALYSIS Bundle-level neutronic analysis (3-D) Fix axial water density distribution (24 points) 9 zones depletion analysis (3 axial and 3 radial) 4-batch refueling scheme with batch dependent power (5.40, 4.73, 4.17, 2.95 MW per bundle) Uncoupled from thermal-hydraulic analysis Sub-channel thermal-hydraulic analysis Stability analysis 7
8 ATTAINABLE BURN-UP FOR THE UPPER BOUND DESIGN Hydride compared to oxide fuel Achieves similar burn-up Decreases the cycle length Parameter Oxide 9x9 Hydride 10x10 Number of fuel rods ~71 96 Number of control rods Control blades 4 P/D Pellet diameter (cm) Average enrichment 3.90% 5% Initial HM mass ratio Single batch BOC k eff Burn-up (GWd/tHM) Fuel residence time (EFPD)
9 POWER PEAKING FACTOR FOR THE UPPER BOUND DESIGN Pin-by-pin power distribution in hydride fuel is extremely flat 1.04 peak 9
10 CONTROL SYSTEM FOR THE UPPER BOUND DESIGN Dispersed control rods PWR s alike Parameters: Number of rods Rods diameter Requirement: Shut-down reactivity margin at least as with control blades in the reference oxide fuel core Parameter Oxide 9x9 Hydride 10x10 Reactivity control system Control blades Control rods 4 control rods (B 4 C) per bundle Control system reactivity worth at hot full power ($) Control system reactivity worth at cold shut-down ($) Diameter slightly larger than fuel rods 10
11 HYDRIDE CORE DESIGNS COMPARISON Parameter Hydride 10x10 (upper bound) CCCR CB Total bundle unit width (cm) Bundles distance (cm) /1.22 Fuel rod OD (cm) P/D Number of fuel rods Control system 4 dispersed control rods 2 corner cruciform control rods Control blades Neutron absorber Natural B 90% enriched B Natural B BOC zero power cold shutdown margin relative to oxide -0.56% +0.00% -0.22% HM load (kg/bundle) Burnup (GWd/tHM) Fuel residence time (EFPD) Radial peaking factor
12 HYDRIDE BUNDLE DESIGNS ARE OPTIMIZED BY ENRICHMENT DISTRIBUTION Constraints from reference oxide design Cycle length Control system worth Power peaking factor Methodology Three axial enrichments As many as needed radial enrichments 12
13 HYDRIDE BUNDLE DESIGNS ARE OPTIMIZED BY ENRICHMENT DISTRIBUTION Cruciform corner control rods Axial Zone Rod A Rod B Rod C Rod D Rod E % 8.27% 6.53% 5.44% 4.79% % 7.40% 5.66% 4.57% 3.92% % 6.53% 4.88% 3.70% 3.05% 13
14 HYDRIDE BUNDLE DESIGNS ARE OPTIMIZED BY ENRICHMENT DISTRIBUTION Control blades Axial Zone Rod A Rod B Rod C Rod D Rod E Rod F Rod G Rod H % 8.15% 6.34% 5.43% 5.43% 4.98% 6.80% 5.89% % 7.70% 5.89% 4.98% 4.53% 4.08% 6.57% 5.44% % 7.25% 5.43% 4.53% 4.08% 3.62% 6.34% 4.98% 14
15 CYCLE LENGTH AND PEAK POWER Parameter Oxide GE14 10x10 CCCB Average enrichment (%) CB Burnable poison Gadolinia IFBA IFBA Average burnable poison load (wt%) 5 (12 rods) 0.50 (uniform) 0.48 (uniform) Cycle length (EFPD) 1,465 1,465 1,465 BOL radial peaking factor BOL axial peaking factor
16 CONTROL SYSTEM Parameter Control system Maximum excess reactivity ($) Reactivity worth at hot full power ($) Reactivity worth at cold shut-down ($) Oxide GE14 10x10 Control blades CCCB Cruciform control rods CB Control blades Shut-down margin ($)
17 REACTIVITY COEFFICIENTS Coolant void (pcm/void%) Time Oxide GE14 10x10 CCCB CB BOC EOC Fuel temperature (pcm/k) Time Oxide GE14 10x10 CCCB CB BOC EOC
18 METHODOLOGY FOR THE THERMAL- HYDRAULIC ANALYSIS Part I: whole core analysis in search for D and P/D giving maximum core power in the range 0.6 < D < 1.6 cm 1.1 < P/D < 1.6 Part II: sub-channel analysis of selected geometries Constraints Parameter Oxide bundle Hydride bundles MCHFR (via EPRI-1 correlation) Fuel Centerline T (ºC) at Steady State Fuel Average T (ºC) at Steady State 1400 Not Applied Clad Surface T (ºC) at Steady State Bundle ΔP (MPa) Subchannel Average Exit Quality (%)
19 MAXIMUM POWER ACHIEVABLE WITH A MPa LIMIT ON THE PRESSURE DROP Parameter Bundle Active Flow Rate (kg/s) MCHFR Max Peak Fuel Temperature ( o C) Max Average Fuel Temperature ( o C) Max Surface Clad Temperature ( o C) Bundle Pressure Drop (MPa) Subchannel-averaged Exit Quality (%) Bundle Power (kw) % difference vs. Oxide 10x10 % difference vs. Hyd. 10x10 Oxide Hydride Hydride CCCR Hydride CB (1.213) 1,568 (2,805) 1,046 (1,400) 310 (349) (0.147) (1.213) 497 (750) Not Applied 306 (349) (0.147) (1.213) 477 (750) Not Applied 305 (349) (0.147) (1.213) 462 (750) Not Applied 304 (349) (0.147) , , , ,
20 MAXIMUM POWER ACHIEVABLE WITH A MPa LIMIT ON THE PRESSURE DROP Parameter Bundle Active Flow Rate (kg/s) MCHFR Max Peak Fuel Temperature ( o C) Max Average Fuel Temperature ( o C) Max Surface Clad Temperature ( o C) Bundle Pressure Drop (MPa) Subchannel-averaged Exit Quality (%) Bundle Power (kw) % difference vs. Oxide 10x10 % difference vs. Hyd. 10x10 Oxide Hydride Hydride CCCR Hydride CB (1.213) 1,873 (2,805) 1,200 (1,400) 309 (349) (0.220) (1.213) 551 (750) Not Applied 310 (349) (0.220) (1.213) 527 (750) Not Applied 309 (349) (0.220) (1.213) 509 (750) Not Applied 308 (349) (0.220) , , , ,
21 MAXIMUM POWER ACHIEVABLE WITH NO LIMIT ON THE PRESSURE DROP Parameter Bundle Active Flow Rate (kg/s) MCHFR Max Peak Fuel Temperature ( o C) Max Average Fuel Temperature ( o C) Max Surface Clad Temperature ( o C) Oxide Hydride Hydride CCCR Hydride CB (1.213) 1,873 (2,805) 1,200 (1,400) 309 (349) (1.213) 551 (750) Not Applied 310 (349) (1.213) 563 (750) Not Applied 311 (349) (1.213) 527 (750) Not Applied 309 (349) Bundle Pressure Drop (MPa) Subchannel-averaged Exit Quality (%) Bundle Power (kw) % difference vs. Oxide 10x10 % difference vs. Hyd. 10x , , , ,
22 FLOW STABILITY WITHOUT PARTIAL LENGTH FUEL RODS Hydride fuel bundles w/o PLFR have better stability than the oxide fuel bundles with PLFR Due to higher thermal conductivity of hydride fuel and liquid metal compared to oxide fuel and helium Parameter Reference oxide 9x9 p limit 0.156/0.234 MPa Hydride 10x10 p limit 0.156/0.234 MPa Decay Ratio 0.111/ /0.094 Decay Ratio if Ox and He /0.126 Decay Ratio if Ox and LM /
23 CONCLUSIONS Use of hydride fuel in BWR s can ideally Greatly simplify the fuel bundle design Eliminating water rods and partial length fuel rods Reducing number of enrichment levels Increasing number of fuel rods per unit core volume by 35% Increase core power density by ~40% By increasing the reactor power level by ~40% By reducing the core height (volume) by ~40% May improve stability Designs compatible with the current BWR core design still offer ~20% power increase compared to oxide fuel 23
24 BACK-UP SLIDES
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