Tritium Breeding Performance Analysis of HCLL Blanket Fusion Reactor Employing Vanadium Alloy (V-5Cr-5Ti) as First Wall Material

Neutronic analysis in the HCLL blanket module has been established, and the calculation was performed by the ITER team, including the first wall (FW). In this study, seven materials have been investigated for FW material by considering characteristics such as high neutron fluence capability, low degradation, under irradiation, and high compatibility for blanket material. A three-dimensional configuration simulated in MCNP5 program codes was performed to investigate the neutronic performance and radiation damage effect. Employing seven candidates are vanadium carbide (VC), titanium carbide (TiC), vanadium alloy (V-5Cr-5Ti), graphite (C), tungsten alloy (W-CuCrZr), ceramic alloy (SiC), and HT-9 to study optimization of FW materials configurated in the HCLL blanket module. This novelty study concludes that vanadium alloy (V-5Cr-5Ti) is becoming a promising material candidate. This alloy has the highest number of neutronic performing for 1.27 TBR and 1.26 in multiplication energy factor in all investigations. Meanwhile, the amount of atomic displacement, hydrogen, and helium production are around 22.31 appm, 765.55 appm, and 281.57 appm, respectively. Even though vanadium alloy has a reasonably high radiation damage effect, it is still tolerable compared to several thresholds of DPA. So, it is considered excellent material for FW. Nevertheless, this alloy can replace after 13.45 years for radiation damage.

[1]  H. Şahin,et al.  Neutronic study on the effect of first wall material thickness on tritium production and material damage in a fusion reactor , 2022, Nuclear Science and Techniques.

[2]  M. Mhadhbi.  Titanium Carbide: Synthesis, Properties and Applications , 2020 .

[3]  Indah Rosidah M,et al.  Studied of Tritium Breeding Ratio on HCLL (Helium Cooled Lithium-Lead) Fusion Blanket by Using MCNP Program , 2020, Journal of Physics: Conference Series.

[4]  Z. Fogarassy,et al.  The Microstructure and strength of a V–5Cr–5Ti alloy processed by high pressure torsion , 2019, Materials Science and Engineering: A.

[5]  Daniele Martelli,et al.  Literature review of lead-lithium thermophysical properties , 2019, Fusion Engineering and Design.

[6]  H. Şahin,et al.  Evaluation of the radiation damage parameters of ODS steel alloys in the first wall of deuterium‐tritium fusion‐fission (hybrid) reactors , 2018 .

[7]  Jean-Charles Jaboulay,et al.  Nuclear analysis of the HCLL blanket for the European DEMO , 2017 .

[8]  Alice Ying,et al.  Blanket/first wall challenges and required R&D on the pathway to DEMO , 2015 .

[9]  Rosaria Villari,et al.  Neutronics requirements for a DEMO fusion power plant , 2015 .

[10]  Z. Su'ud,et al.  Optimization of tritium breeding and shielding analysis to plasma in ITER fusion reactor , 2015 .

[11]  T. Muroga,et al.  Present Status of Vanadium Alloys for Fusion Applications , 2014 .

[12]  T. Guilbert,et al.  French investigation of a new V–4Cr–4Ti grade: CEA-J57 – Fabrication and microstructure , 2012 .

[13]  N. M. Larson,et al.  ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data , 2011 .

[14]  J.-F. Salavy,et al.  HCLL TBM design status and development , 2011 .

[15]  K. Shibata,et al.  JENDL-4.0: A New Library for Nuclear Science and Engineering , 2011 .

[16]  Rosaria Villari,et al.  Neutronics experiments on HCPB and HCLL TBM mock-ups in preparation of nuclear measurements in ITER , 2010 .

[17]  I. Kodeli,et al.  Use of Nuclear Data Sensitivity and Uncertainty Analysis for the Design Preparation of the HCLL Breeder Blanket Mockup Experiment for ITER , 2008 .

[18]  H. Şahin,et al.  Monte Carlo calculation for various enrichment lithium coolant using different data libraries in a hybrid reactor , 2008 .

[19]  R. Macfarlane,et al.  The NJOY Nuclear Data Processing System , 2008 .

[20]  H. Şahin.  Monte Carlo calculation of radiation damage in first wall of an experimental hybrid reactor , 2007 .

[21]  R. Neu,et al.  Tungsten as first wall material in fusion devices , 2007 .

[22]  E. Villedieu,et al.  Overview of the ITER-like wall project , 2007 .

[23]  G. Kazantzis.  CHAPTER 44 – Tungsten , 2007 .

[24]  T. Muroga,et al.  Development of fabrication technology for low activation vanadium alloys as fusion blanket structural materials , 2006 .

[25]  T. Muroga.  Vanadium Alloys for Fusion Blanket Applications , 2005 .

[26]  Ulrich Fischer,et al.  Neutronic design issues of the WCLL and HCPB power plant models , 2003 .

[27]  Patrick J. Griffin,et al.  INTERNATIONAL REACTOR DOSIMETRY FILE: IRDF-2002 , 2003 .

[28]  M. Übeyli.  On the Tritium Breeding Capability of Flibe, Flinabe, and Li20Sn80 in a Fusion-Fission (Hybrid) Reactor , 2003 .

[29]  David L. Smith,et al.  Vanadium-base alloys for fusion first-wall/blanket applications , 2000 .

[30]  W. Lengauer,et al.  Order-disorder phase transformations and specific heat of nonstoichiometric vanadium carbide , 1999 .

[31]  M. I. Solonin,et al.  Vanadium alloys as structural materials for fusion reactor blanket , 1996 .

[32]  J. F. Briesmeister.  MCNP-A General Monte Carlo N-Particle Transport Code , 1993 .

[33]  S. Yiftah,et al.  The (n,2n) and (n,3n) Reactions of Lead, A Potential Neutron Amplifier for Fusion Blankets , 1985 .

[34]  E. Greenspan,et al.  High-energy multiplication blankets for CAT-D fusion reactors , 1984 .

[35]  J. T. Adrian Roberts,et al.  Fusion First-Wall/Blanket Materials , 1981 .

[36]  C. Barnes,et al.  Recent results from the PLT tokamak , 1978 .