SUPERCRITICAL WATER NUCLEAR STEAM SUPPLY SYSTEM: INNOVATIONS in MATERIALS, NEUTRONICS and THERMAL-HYDRAULICS

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1 SUPECITICAL ATE NUCLEA STEAM SUPPLY SYSTEM: INNOVATIONS in MATEIALS, NEUTONICS and THEMAL-HYDAULICS 1 M. Anderon, P. Hu,.Jain, V.Sehadri, P.Brook, K.Sridharan, P. ilon, M.Corradini Nuclear Engr. & Engr. Phyic, U-Madion Of Nucl ear Sytem D.Cho, T.Kim, S.Lomperki eactor Analyi and Engineering, Argonne National Lab Of Nucl ear Sytem of Nuclear Sytem Nuclear Engr & Engr Phyic, Univerity of iconin - Madion eactor Analyi & Engineering Diviion

2 SC eearch Objective: 2 Deign and fabrication of out-of-pile SC tet facilitie for current & future utilization in &D Fuel-cladding urface modification to improve cladwater compatibility, corroion and wear (Tak I: U Madion i the lead - Anderon/Sridharan) Neutronic analye of thermal SC core deign with modified fuel-cladding material (Tak II: Argonne i the lead with U aiting - Kim/ilon) Fundamental tudy of SC tability and heat tranfer under natural/forced circulation condition (Tak III: Argonne i lead with U - Cho/Anderon) Of Nucl ear Sytem of Nuclear Sytem Nuclear Engr & Engr Phyic, Univerity of iconin - Madion eactor Analyi & Engineering Diviion

3 3 SC Progre in FY 2002 Cladding ample obtained, PSII urface modification and low-temperature tet begun SC corroion and thermal-hydraulic loop deign/contruction completed at U (final etup). Neutronic code benchmarking begun with nominal SC thermal deign with improvement Thermal-hydraulic heat tranfer and tability model developed and analye begun SC imulant CO 2 flow tability loop deigned and contruction begun at ANL Of Nucl ear Sytem of Nuclear Sytem Nuclear Engr & Engr Phyic, Univerity of iconin - Madion eactor Analyi & Engineering Diviion

4 Deign of SC loop Loop preure control Preurizer 4 Building Cooling ater Coolant Filter Coolant Pump Heat Exchanger Throttle-Cooling Coil Cooling manifold Drain HPLC Pump Primary purpoe i to tudy corroion in flowing ytem Coolant eevoir Corroion Sample Tet Section ater Filtration Sytem ectangular loop 3m x 2m Loop I.D m Loop deign, contruction, material and teting to ASME code 3.00 m Upper Heating Manifold 32 K Total Lower Heating Manifold 40 K Total Chemitry control ater makeup iconin of Intitute Nuclear of Sytem Nuclear Sytem Of Nucl ear Sytem 2.04 m Nuclear Engr & Engr Nuclear Phyic, Engr & Univerity Engr Phyic, of iconin Univerity - Madion of iconin - Madion eactor Analyi & Engineering Diviion Of Nucl ear Sytem

5 ANL - SC Stability Loop 5 EXHAUST GAYLOC FITTING T 25 k CHILLE T ELIEF Primary purpoe i to tudy heat tranfer and SC CO 2 tability PESSUIZE 1 m He CO 2 LEVEL DETECTO ELIEF P EXHAUST 2 m COLD SIDE P EXTENAL ULTASONIC FLO METE P HOT SIDE PIPE, 1/2" SCH. 80, SST 0.840" OD X 0.546" ID X 0.147" LOOP DESIGN PESSUE: 100 BA (1470 pi) COPPE CONNECTION SILVE SOLDEED TO PIPE TC'S ON OUTSIDE OF PIPE 2" SCH 80 PIPE T T T T T T T T T T 1/4" SST TUBE P T T T 1 m P 0-60 VAC 5000 A He PUMP CO VAC 770 A DAING: CO2 LOOP CONCEPTUAL DESIGN DAING NO.: CO2L2 DAN BY: D. KILSDONK DATE: 4/11/02 FILE: CO2_LOOP_2.DG(AC70) Of Nucl ear Sytem of Nuclear Sytem Nuclear Engr & Engr Phyic, Univerity of iconin - Madion eactor Analyi & Engineering Diviion

6 6 KEY OBSEVATIONS on SC Current deign have not taken full advantage of the neutronic/thermal-hydraulic coupling that i inherent in SC ytem (e.g., economic) Material i the enabling technology and need bae funding that parallel reactor development Chemitry impact on material i a key feedback The key operational afety iue i control/tability The key accident afety iue i accident timing (i.e., critical flow, degraded heat tranfer, ytem timing) Of Nucl ear Sytem of Nuclear Sytem Nuclear Engr & Engr Phyic, Univerity of iconin - Madion eactor Analyi & Engineering Diviion

7 hat about Neutron? 7 The larget data gap in both upercritical and ubcritical radiolyi i in the yield from neutron radiolyi. (McCracken, et al, 1998) ued ophiticated Monte Carlo cattering code and reaonable aumption about the energy dependence of yield in heavy ion radiolyi. Neutron yield have been reported in ome experiment Univerity of Tokyo YAYOI fat reactor by Sunaryo, et al.(sunaryo, et al, 1994; 1995; 1995a) eult of the two group do not agree. McCracken et al (McCracken, et al 1998) ugget the Tokyo reult are flawed by impurity contamination. Amazingly, there are no experimental meaurement of neutron radiolyi yield at any temperature for the P neutron pectrum. Of Nucl ear Sytem of Nuclear Sytem Nuclear Engr & Engr Phyic, Univerity of iconin - Madion eactor Analyi & Engineering Diviion

8 SC chemitry at U (Neutron radiolyi) 8 Nuclear reactor can produce a flux of neutron ufficient to caue radiolyi of SC thi will allow u to undertand the chemitry pecifically the O 2 concentration which can be added to our flow loop to tet corroion in typical reactor coolant compoition Of Nucl ear Sytem of Nuclear Sytem Nuclear Engr & Engr Phyic, Univerity of iconin - Madion eactor Analyi & Engineering Diviion

9 SC Chemitry Loop in the UN Preheater 9 Beam port number 2 in U nuclear reactor Anticipated neutron flux at temp i ~ n/cm 2 / (0.16 watt/g) which i ufficient to reult in detectable level of radiolyi (1.6e-6 mole/liter/) Schematic of propoed loop for SC neutron radiolyi ection 1 ection 2 ection 3 ection 4 Neutron hield Heating ection 92 cm 48 cm 94 cm 89 cm DAQ HPLC pump water reervoir Irradiation volume Graphite moderator Pb gamma/beta hielding 6 cm ater hielding water bath H2O ampling Of Nucl ear Sytem of Nuclear Sytem Nuclear Engr & Engr Phyic, Univerity of iconin - Madion eactor Analyi & Engineering Diviion

10 Novel SC reactor deign propoed by ANL/U 10 Control rod Coolant outlet Coolant outlet Coolant inlet ~ 0.7g / cm 3 ~ 0.1g / cm 3 ~ 0.7g / cm 3 Coolant inlet Inner core (fat pectrum) Outer core (thermal pectrum) Thermal hield Core plate ~ 0.4g / cm 3 Of Nucl ear Sytem of Nuclear Sytem Nuclear Engr & Engr Phyic, Univerity of iconin - Madion eactor Analyi & Engineering Diviion