European Collaboration on Lead Cooled Nuclear Reactor Development

Transcription

1 European Collaboraton on Lead Cooled Nuclear Reactor Development Jerzy Cetnar Akadema Górnczo-Hutncza w Krakowe 7. Program Ramowy, Dzeń nformacyny Euratom Fsson 2010; Warszawa 8 XII

2 Lead-cooled European Advanced Demonstraton Reactor - Leader The development to a conceptual level of: Lead Fast Reactor Industral sze plant Scaled demonstrator of the LFR (Lead Fast Reactor) technology Mlestones: The proect s commtted to the desgn of a scaled/plot plant to be constructed n the relatvely short term. The focus of the frst part of actvty wll be the resolutons of the key ssues emerged n the frame of the proect to reach a new reference reactor confguraton Ths updated reactor confguraton of an ndustral sze LFR wll be used to desgn a low cost and fully representatve scaled down prototype of a sutable sze. 7. Program Ramowy, Dzeń nformacyny Euratom Fsson 2010; Warszawa 8 XII

3 Leader Consortum 7. Program Ramowy, Dzeń nformacyny Euratom Fsson 2010; Warszawa 8 XII

4 LFR demonstrator plant obectves Demonstrate that: the adopted nnovatve desgn and technology acheves the hgh safety standards, whch would be requred at the tme of ther deployment, the fuel cycle can be closed, the non-prolferaton resstance s enhanced, a hgh avalablty factor s reached the economc compettveness target s reached. The desgn s complant wth GIF goals 7. Program Ramowy, Dzeń nformacyny Euratom Fsson 2010; Warszawa 8 XII

5 Vertcal secton of the reactor 7. Program Ramowy, Dzeń nformacyny Euratom Fsson 2010; Warszawa 8 XII

6 Pump and steam generator assembly 7. Program Ramowy, Dzeń nformacyny Euratom Fsson 2010; Warszawa 8 XII

7 AGH expertse Development of numercal methods for nuclear system desgn dervaton of a general soluton for Bateman equatons of nuclear transmutaton. (Currently the paper: J. Cetnar General soluton of Bateman equatons for nuclear transmutatons Annals of Nuclear Energy Volume: 33, Issue: 7, May, 2006, pp s the second on the most downloaded artcles n Annals of Nuclear Energy ) Development of calculaton codes for neutronc and burnup calculatons: BISON-C and MCB (currently verson 5) devoted for reactor systems unque features not avalable n other codes. (cooperaton wth KTH) Contrbutons to Accelerator Drven Systems - ADS development n EU EURATOM FP4, FP5, FP6 proects: IABAT MUSE PDS-XADS EUROTRANS Contrbutons to crtcal reactor developments. EU EURATOM FP6 proects: PUMA 7. Program Ramowy, Dzeń nformacyny Euratom Fsson 2010; Warszawa 8 XII

8 MCB Methodology MCB: Monte Carlo Contnuous Energy Burnup Code; (uses MCNP for trasnport calc.) Includes calculatons of: egenvalue of crtcal or subcrtcal system neutron transport n fxed source mode burnup, decay, transmutaton and actvaton radotoxcty assessment statstcal analyss of transmutatons burnup perturbaton Allows the user to smulate: full 3D heterogenous geometry fuel shufflng fuel reprocessng mult-cyclng contnuous feedng of materals control rod nserton or wthdrawal 7. Program Ramowy, Dzeń nformacyny Euratom Fsson 2010; Warszawa 8 XII

9 9 7. Program Ramowy, Dzeń nformacyny Euratom Fsson 2010; Warszawa 8 XII 2009 Bateman Equatons Soluton (general case) [ ] ( ) m m m n m t t t A = = Ω = µ µ α, 0 1! exp ) ( 1, = = n m α = = = = = + = Ω h h h n k k n l l l h k k k k n k h h , 1 2, δ µ µ L thus partcularly 1 0 Ω, =

10 IAEA- ADS benchmark (Thorum fuel cycle) Tme evoluton of k eff from the ntal value of KTH-MCB wth dfferent cross-secton data lbrares. MCB precson of the order of 0.1%. IPPE, dffuson IRPCP, dffuson PSI, JEF 2.2 JAERI CEA-Cad. KTH - MCB JEF PSI, JENDL 3.2 KTH - MCB JEND L ENEA KTH - MCB ENDFB 0,98 k-eff (t=0) ~ ,97 0,96 0,95 k-eff. 0,94 0,93 0,92 0,91 0, Days 7. Program Ramowy, Dzeń nformacyny Euratom Fsson 2010; Warszawa 8 XII

11 Evoluton of k eff n tme n IAEA-ADS benchmark Comparson of MCB results wth dfferent lbrares: JEF2.2, JENDL3.2 and ENDFB6.5 startng from dfferent ntal k eff -values. 0,99 0,98 0,97 0,96 k-eff (t=0) ~ 0.98 k-eff (t=0) ~ 0.96 k-eff (t=0) ~ 0.94 KTH - MCB JEF KTH - MCB JENDL KTH - MCB ENDFB keff 0,95 0,94 0,93 0, Days 7. Program Ramowy, Dzeń nformacyny Euratom Fsson 2010; Warszawa 8 XII

12 Radotoxctyof LBE after 20 years rradaton (PDS-XADS) Radotoxcty [Sv] LBE-Cooled XADS Prmary Loop Total Po210 B207 Hg194 Tl204 B210m B210 Sr90 H3 B205 B206 Hg Coolng Tme [years] 7. Program Ramowy, Dzeń nformacyny Euratom Fsson 2010; Warszawa 8 XII

13 NITRIDE FUEL CORE (wth Zr) (85%TD) INNER SA I: 20% vol: ZrN 80% vol: (U,Pu,MA)N 13.5% Pu, 2.5%MA INNER SA II: 10 % vol: ZrN 90% vol: (U,Pu,MA)N 13.5% Pu, 2.5%MA OUTER SA I: (U,Pu,MA)N 17% Pu, 5%MA OUTER SA II: (U,Pu,MA)N 20% Pu, 5%MA 7. Program Ramowy, Dzeń nformacyny Euratom Fsson 2010; Warszawa 8 XII

14 Tme evolutons, reactvty coeffcents 1,01 Crtcalty Evoluton; CR nserted 33,5 cm 1,24 1,22 Radal form factor evoluton; CR nserted 33,5 cm K-eff 1, ,995 Radal form factor 1,2 1,18 1,16 1,14 0, tme [fpd] 1, tme [fpd] 7. Program Ramowy, Dzeń nformacyny Euratom Fsson 2010; Warszawa 8 XII

15 Axally ntegrated power factor n ntrde core over 1800 day cycle 7. Program Ramowy, Dzeń nformacyny Euratom Fsson 2010; Warszawa 8 XII