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1、Study on Conceptual Design of Tritium Production Reactor based on STHE Kaihui HUANG JinhuaDivision 105 of Southwestern Institute of Physics, Chengdu, P. R. China *Contents lComparison of tritium productionlNeutronics design of ST-TPRlPreliminary overall design of ST-TPRlConclusion and future workCom
2、parison of Tritium ProductionlD-T fusion is the most probable solution for fusion energyComparison of tritium production facilitiesFacilitiesTimeReactor power, MWthFuelTBR (net)Production (Kg/a)availa bilityTritium cost,$/g*HWR19882500235U- Fission0.8770%101,000MHTGR198828000.87.870%55,600APT1989400
3、1.6GeV,P-beam Pb(Liq.)target40- 506.870%162,000TM1982540D-T Fusion for MCF0.6710.870%36,200TOK19825700.529.170%48,600TTPR199750010000.432.025%Not givenICF-TPR1985532D-T Fusion for ICF1.0816.970%12,300SIRIUS-T198614100.9033.670%10,300*1990US$, reference “comparison of tritium production reactors”,Fus
4、.technol. Vol 19, 1991Tritium Production Approaches1. Nuclear reaction in nature; 2. Nuclear explosion; 3. Fission reactor:lHeavy-water reactor;lLight-water reactor; 4. Accelerator production tritium; 5. Breeding zone in fusion reactor.Advantages of APTl No fissile materials l No spent nuclear fuel
5、produced l Produces very little low-level and no high-level radioactive waste per year l No chance of a criticality accident l Minimal environmental effects l No nuclear proliferation issues l Engineering simplicity provides inherent safety advantages l Constant extraction of tritium l Immediate shu
6、tdown l Easily scaled to stockpile needs Disadvantage: too expensive, high up to 910B$Operating parametersAPTESSTritium production/a ,kg3.0 Overall availability 71% Beam current (mA)1003.8Beam energy (MeV)17001344Beam power (MW)1705.0Proton flux (mA/cm2)28Peak proton flux (mA/cm2)33Peak neutron flux
7、 (n/cm2.s)1.0x1015Gaps between requirements and state-of-the-arts for APTScientists predicted that the time scale for the APT technology development is 20 years, comparable to that for a fusion-based tritium production development. However, as an alternative approach to producing tritium, whether AP
8、T can be decided as the better one depends on the development of both technologies.*ESS: European Spallation SourceAdvantages of fusion-based tritium productionlAs an intermediate application of fusion energy, fusion-based neutron source (NS) is highly recommended to develop, so as to contribute to
9、fusion science and technology development.lCompared with Accelerator-based NS, a localized source, fusion-based NS is volumetric source with a large surface area available for locating tritium production assemblies in high neutron flux, and has much greater high-neutron- flux irradiation volume. Ano
10、ther sequence is that the max. neutron radiation damage rate to the FW material will be much less for a distributed fusion source.lDevelopment of the vast majority of the physics and technology needed for a fusion NS has been carried forward as an international collaboration in support of ITER, wher
11、eas the accelerator development would require a substantial addition R 2D results as design point.lTritium production objective: 1kg/a with availability 40%Neutronics design of ST-TPRNeutronics design of ST-TPRNeutronics codes flow in calculationMajor dimension consideration，gross tritium product pe
12、r year ：Except fusion fuel cycle, leakage, etc., net tritium：Set neutron wall loading,n=1.0MW/m2，plant factor,PF=40%，the relationship between blanket first wall radius rin，rout and TBR for 1kg excess tritium production ：Neutronics design for ST-TPRPlasma core consideration for 1kg/a excess tritium p
13、roduction:lThe tritium consumption by the fusion neutron source is 5.6PF kg/a per 100MW of fusion power. Fusion power (MW)TBR for PF=0.4TBR for PF=0.5TBR for PF=0.81001.45(2.24)*1.36(2.8)1.23(4.48)2001.227(4.48)1.18(5.6)1.114(8.96) 4001.114(8.96)1.09(11.2)1.06(17.92)Neutronics design for ST-TPRl For
14、 production of 1kg/a excess tritium，if PF0.4， actually 3.24kg /a is produced for fusion power 100MW.* Initial tritium inventory is not included1D neutronics calculation modelZones included and material compositions for 1D calculation：lCenter post，ie, CS，material: Al，he-4(coolant)；lInboard shield，SS3
15、16,B4C,and He；lInboard V.V.，SS316 and He；lInboard tritium production blanket，TRITIUM BREEDER: 6Li(enrichment 92%) and 7Li; NEUTRON MULTIPLIER: Be，SS316 and He；lInboard First Wall，Be, He and SS316；lInner SOL；lPlasma zone；lOutside SOL；lOutboard First Wall，material similar as inboard first wall；lOutboa
16、rd tritium production blanket, main TPB, material similar as inboard TPB, different fractions；lOutside V.V.， SS316 and He ；lOutboard shield，main shield， SS316,B4C,and He.option 1 for neutronics calculationTritium was produced only in outboard TPB, which was divided 2 zones for both neutron multiply and tritium breed, respectively.R 0 32.0 33 40.0 264. 270
