A preliminary design study for the HYPER system

Nuclear Engineering and Design

Volumn 219, Issue 3, 2003, Pages 207-223

  Park, Won S ^a   Song, Tae Y ^a   Lee, Byoung O ^a   Park, Chang K ^a  

^a Korea Atomic Energy Research Institute   (South Korea)

Author keywords

[No Author keywords available]

Indexed keywords

COOLANTS; FISSION PRODUCTS; ISOTOPES; NEUTRONS; RADIOACTIVE ELEMENTS; RADIOACTIVE WASTES; SPENT FUELS; STEEL;

HYBRID POWER EXTRACTION REACTOR (HYPER) SYSTEMS;

LIGHT WATER REACTORS;

EID: 0037290612     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0029-5493(02)00207-8     Document Type: Article

References (30)

1. ATW, 1999. A Roadmap for Developing Accelerator Transmutation of Waste (ATW) Technology, DOE/RW-0519.
2. Adamov E., et al. The next generation of fast reactors. Nuclear Engineering and Design. 173:1997;143-150.
3. ANSYS User's Manual for Revision 5.0.
4. Bowman, C. et al., 1992. Nuclear Energy Generation and Waste Transmutation Using an Accelerator Driven Intense Thermal Neutron Sources. LANL Report LA-UR-91-2601, LANL.
5. Bowman, C., 1998. Once-Through Thermal Spectrum Accelerator-Driven System for LWR Waste Destruction without Reprocessing: Tier-1 Description, ADNA Report, ADNA Corporation, ADNA/98-04, August.
6. Chung, Jong Sung et al., 2000. Verification of SMART Neutronics Design Methodology by the MCNAP Monte Carlo Code. ANS/ENS International Meeting, Washington DC, USA.
7. FLUENT Tutorial Guide, 1993. Version 4.2, Fluent Incorporated.
8. Hwang, W. et al., 2001. Analysis on the Temperature Profile and the Thermal Conductivities of the Metalic and the Dispersion Fuel Rods for HYPER. Korean Nuclear Society Spring Meeting.
9. Kim, Chang H. et al., 2001. Sub-channel Analysis of HYPER Single Fuel Assembly Using SLTHEN Code. Korean Nuclear Society Fall Meeting.
10. Kim, Y.H., Park, W.S., Song, T.Y., 2001. Optimization of H/D (Height-to-Diameter) Ratio in ADS. Korean Nuclear Society Spring Meeting.
11. Kim, Y.H., Park, W.S., 2000. A Study on Burnable Absorber for a Fast Subcritical Reactor HYPER. 6th OECD/NEA P&T Meeting, Madrid, Spain.
12. Kim, Young G. et al., 2001. Thermal Hydraulic Conceptual Design Characteristics of KALIMER Breakeven Core. Korean Nuclear Society Spring Meeting.
13. Knebel, J. et al., 2001. Thermalhydraulic and Material Specific Investigations into the Realization of an Accelerator Driven System (ADS) to Transmute Minor Actinides FZK Report, FZK6618.
14. Lee, B. et al., 2001. A Mechanistic Deformation Model of TRU Metal Dispersion Fuel for HYPER. Korean Nuclear Society Spring Meeting.
15. Meyer, M.K., Lee, B.O., 2000. Thermal Conductivity of Zirconium Matrix Dispersion Fuel Inter-Office Memorandum, MKM-00-DRAFT, ANL.
16. OECD/NEA, 1998. Status and Assessment Report on Actinide and Fission Product Partitioning and Transmutation System Studies, NEA/PTS/DOC(98)4.
17. OECD/NEA, 2001. NDC Comparative Study of ADS and FR in Advanced Nuclear Fuel Cycle, to be published at the end of 2001.
18. Park, Won S. et al., 1999. TRU Incineration Characteristics of Thermal and Fast Subcritical Reactors. Annals of Nuclear Energy, vol. 26.
19. Park, W.S. et al., 2000. Fission Product Target Design for HYPER System. 6th OECD/NEA P&T Meeting, Madrid, Spain.
20. Prael, Richard E., Lichtenstein Henry, 1989. User Guide to LCS: The LAHET Code System, LA-UR-89-3014 Los Alamos National Lab.
21. Rubbia, C. et al., 1995. Conceptual Design of a Fast Neutron Operated High Power Energy Amplifier CERN Report, CERN/AT/95-44(ET), European Organization for Nuclear Research.
22. Salvatores, S. et al., 1997. The Potential of Accelerator-Driven Systems for Transmutation or Power Production Using Thorium or Uranium Fuel Cycles, Nuclear Science and Engineering 126, 333-340.
23. Salvatores, Bauer, Heusener, 1999. The MEGAPIE Initiative-Executive Outline and Status as per November 1999. MPO-1-GB-6/0_GB.
24. Sasa, T. et al., 2001. 'Conceptual Design Study of ADS Experimental Facilities,' Accelerator Applications/Accelerator Driven Transmutation Technology and Applications '01 (AccApp/ADTTA '01), Reno, Nevada, USA, November 12-15.
25. Song, T.Y. et al., 2000. Thermal and Stress Analysis of HYPER Target System. 6th OECD/NEA P&T Meeting, Madrid, Spain.
26. Tang, Y.S. et al., 1978. Thermal Analysis of Liquid-metal Fast Breeder Reactors American Nuclear Society.
27. Waltar, Alan E., Reynolds, Albert B., 1981. Fast Breeder Reactors Pergamon Press.
28. Wood, J.C. et al., 1984. Reduced Enrichment Fuels for Canadian Research Reactors-Fabrication and Performance Proc. of the 1984 International meeting in RERTR, Argonne, IL, ANL/RERTR/TM-6, October 15-18, pp. 167-183.
29. Yachmenyov, G.S. et al., 1998. Problems of Corrosion of Constructral Materials in Lead-Bismuth Coolant. Proc. Int. Conf. on Heavy Liquid Metal Coolants in Nuclear Technologies, Obninsk, vol. 1, pp. 133-140.
30. Yang W.S. An LMR core thermal-hydraulics code based on the ENERGY model. Journal of Korean Nuclear Society. 29:(5):1997;406-416.