Studies on the feasibility of the lwrs waste-thorium in-core fuel cycle in the gas turbine-modular helium reactor

Journal of Nuclear Science and Technology

Volumn 43, Issue 11, 2006, Pages 1379-1394

  Talamo, Alberto ^a  

^a ROYAL INSTITUTE OF TECHNOLOGY   (Sweden)

Author keywords

Fertile; Gas cooled; Graphite moderated; GT MHR; MCB; Thorium; TRISO; Waste

Indexed keywords

GAS TURBINES; HELIUM; NUCLEAR FUELS; REACTOR CORES; SOLID WASTES; THORIUM;

FERTILE THORIUM; GAS TURBINE-MODULAR HELIUM REACTOR; PACKING FRACTIONS; TRISO PARTICLES;

LIGHT WATER REACTORS;

EID: 33846503796     PISSN: 00223131     EISSN: None     Source Type: Journal    
DOI: 10.1080/18811248.2006.9711232     Document Type: Article

References (19)

1. General Atomics, GT-MHR Conceptual Design Description Report, GA/NRC-337-02, (2002).
2. M. P. Labar, W. A. Simon, Comparative Economics of the GT-MHR and Power Generation Alternatives, GA-A21722, General Atomics, (1994).
3. A. Baxter, M. Fikani, Reactor Based Transmutation—Physics Studies of the Gas-Cooled Graphite-Moderated Deep Burn Reactor, GA-501-0-TRT-000140, General Atomics, (2002).
4. A. Talamo, W. Gudowski, “Performance of the Gas TurbineModular Helium Reactor fuelled with different types of fertile TRISO particles,” Ann. Nucl. Energy, 32[16], 1719-1749 (2005).
5. A. Talamo, W. Gudowski, “Comparative studies of JENDL-3.3, JENDL-3.2, JEFF-3, JEF-2.2 and ENDF/B-6.8 data libraries on the Monte Carlo continuous energy modeling of the Gas Turbine-Modular Helium Reactor operating with thorium fuels,” J. Nucl. Sci. Technol., 42[12], 1040-1053 (2005).
6. K. Minato, T. Ogawa, T. Koya, et al., “Retention of fission product cesium in ZrC-coated fuel particles for high-temperature gas-cooled reactors,” J. Nucl. Mater., 279, 181-188 (2000).
7. K. Minato, T. Ogawa, K. Sawa, et al., “Irradiation experiment on ZrC-coated particles for high temperature gas cooled reactors,” Nucl. Technol., 130, 272-281 (2000).
8. K. Minato, K. Fukuda, H. Sekino, et al., “Deterioration of ZrC-coated fuel particle caused by failure of pyrolitic carbon layer,” J. Nucl. Mater., 252, 13-21 (1998).
9. K. Minato, T. Ogawa, K. Fukuda, H. Sekino, I. Kitagawa, N. Mita, “Fission product release from Zr-coated fuel particles during post-irradiation heating at 1800 and 2000°C,” J. Nucl. Mater., 249, 142-149 (1997).
10. M. B. Richards, R. K. Luu, Design of Coated Particle Driver and Transmutation Fuels, GA-224-0-RDE-000135, General Atomics, (2002).
11. M. A. Feltus, “Overview of the DOE advanced gas reactor fuel development and qualification program and gas reactor R&D,” IAEA Technical Meeting on ''Current Status and Future Prospects of Gas Cooled Reactor Fuels,” Vienna, Austria, (2004).
12. R. Plukiene, D. Ridikas, “Modeling of HTRs with Monte Carlo: from a homogeneous to an exact heterogeneous core with microparticles,” Ann. Nucl. Energy, 30[15], 1573-1585 (2003).
13. J. F. Briesmeister, A General Monte Carlo N-Particle Transport Code—Version 4c, LANL, LA-13709-M, (2002).
14. J. Cetnar, W. Gudowski, J. Wallenius, K. Tucek, “Simulation of nuclide transmutation with Monte-Carlo Continuous Energy Burnup Code (MCB1C),” Proc. Accelerator Application 2001 and ADTTA 2001 Nuclear Application in the New millennium, Reno, USA, (2001).
15. J. Cetnar, W. Gudowski, J. Wallenius, MCB: A Continuous Energy Monte Carlo Burnup Simulation Code, in Actinide and Fission Product Partitioning and Transmutation, EUR 18898 EN, OECD/NEA 523, (1999).
16. R. Jacqmin, R. Forrest, J. Rowlands, A. Nouri, M. Kellett, “Status of the JEFF-3 Project,” Proc. Int. Conf. on Nuclear Data for Science and Technology, Oct. 7-12, 2001, Vol. 1, p. 54 (2002).
17. K. Shibata, T. Kawano, T. Nakagawa, O. Iwamoto, J. Katakura, T. Fukahori, S. Chiba, A. Hasegawa, T. Murata, H. Matsunobu, T. Ohsawa, Y. Nakajima, T. Yoshida, A. Zukeran, M. Kawai, M. Baba, M. Ishikawa, T. Asami, T. Watanabe, Y. Watanabe, M. Igashira, N. Yamamuro, H. Kitazawa, N. Yamano, H. Takano, “Japanese Evaluated Nuclear Data Library Version 3 Revision-3: JENDL-3.3,” J. Nucl. Sci. Technol., 39, 1125 (2002).
18. ENDF/B-VI, The US Evaluated Nuclear Data Library, IAEA-NDS-110, Rev. 6, (1995).
19. A. Talamo, W. Gudowski, “Adapting the deep burn In-core fuel management strategy for the Gas Turbine-Modular Helium Reactor to a uranium-thorium fuel,” Ann. Nucl. Energy, 32[16], 1750-1781 (2005).