Report on intermediate results of the IAEA CRP on 'Studies of advanced reactor technology options for effective incineration of radioactive waste'

Energy Conversion and Management

Volumn 49, Issue 7, 2008, Pages 1810-1819

  Maschek, W ^a   Stanculescu, A ^b   Arien, B ^c   Bai, Y ^k   Chabert, Ch ^d   Chebeskov, A A ^f   Chen, X ^a   da Cruz, D F ^e   Dekoussar, V ^f   Devan, K ^h   Dulla, S ^g   Gopalakrishnan, V ^h   Feynberg, O ⁱ   Harish, R ^h   Ignatiev, V ⁱ   Kophazi J ^j   Li, J ^k   Malambu, E ^c   Mohanakrishnan, P ^h   Morita, K ^l   Pandikumar, G ^h   Peneliau, Y ^d   Ravetto, P ^g   Rineiski, A ^a   Schikorr, M ^a   Srivenkatesan, R ^m   Subbotin, V ⁱ   Surenkov, A ⁱ   Szieberth, M ^j   Taczanowski, S ⁿ   Tucek K ^q   Vertes, P ^o   Vorotyntsev, M ^f   Uhlir J ^p   Wider, H ^q   Wu, Y ^k   Zakirov, R ⁱ   Zheng, S ^k   more..

^a KARLSRUHE INSTITUTE OF TECHNOLOGY   (Germany)

^b INTERNATIONAL ATOMIC ENERGY AGENCY   (Austria)

^c BELGIAN NUCLEAR RESEARCH CENTRE   (Belgium)

^d IRFM   (France)

^e NUCLEAR RESEARCH AND CONSULTANCY GROUP NRG   (Netherlands)

^f INSTITUTE OF PHYSICS AND POWER ENGINEERING   (Russian Federation)

^g POLITECNICO DI TORINO   (Italy)

^h INDIRA GANDHI CENTRE FOR ATOMIC RESEARCH   (India)

ⁱ KURCHATOV INSTITUTE   (Russian Federation)

^j BUDAPEST UNIVERSITY OF TECHNOLOGY AND ECONOMICS   (Hungary)

^k INSTITUTE OF GEOLOGY AND GEOPHYSICS   (China)

^l KYUSHU UNIVERSITY   (Japan)

^m BHABHA ATOMIC RESEARCH CENTRE   (India)

ⁿ AGH UNIVERSITY OF SCIENCE AND TECHNOLOGY   (Poland)

^o KFKI ATOMIC ENERGY RESEARCH INSTITUTE   (Hungary)

^p NUCLEAR RESEARCH INSTITUTE   (Czech Republic)

^q JOINT RESEARCH CENTRE   (Italy)

more..

Author keywords

Benchmark; Coordinated research project; Dynamics; IAEA; Kinetics; Transients; Transmutation systems

Indexed keywords

BENCHMARKING; FAST REACTORS; GAS COOLED REACTORS; NUCLEAR MATERIALS SAFEGUARDS; WASTE INCINERATION;

BURN-UP BEHAVIOR; COORDINATED RESEARCH PROJECTS; DECAY HEAT; TRANSMUTATION SYSTEMS;

RADIOACTIVE WASTE DISPOSAL;

EID: 44149107095     PISSN: 01968904     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.enconman.2007.08.018     Document Type: Article

References (44)

1. Maschek W, Stanculescu A. IAEA CRP on studies of advanced reactor technology options for effective incineration of radioactive waste, GLOBAL 2005, Tsukuba, Japan, October 9-13; 2005.
2. Lee SL et al. Conceptual design of PFBR core, conceptual designs of advanced fast reactors, TCM, Kalpakkam, India, 3-6 October, IAEA-TECDOC-907; 2005.
3. Mohanakrishnan P, Physics design of core, PFBR/01113/DN/1049 (Rev.C), Indira Gandhi Centre for Atomic Research, Kalpakkam; 2004.
4. Poplavskiiet V.M., et al. BN-800 as a new stage in the development of fast sodium-cooled reactors. Atomic Energy 96 (2004) 386-390
5. Bagdasarov YuE et al. Reactor BN-800 - a new stage in fast reactor development. In: Paper presented at the international symposium on fast breeder reactors. IAEA-SM 284/41, Lyon, France, 22-26 July; 1986.
6. Tucek K, Carlson J, Wider H. Comparison of sodium and lead-cooled fast reactors regarding severe safety and economical issues. In: Proceedings of 13th international conference on nuclear engineering ICONE13, Beijing, China; 2005.
7. Carlson J, Tucek KK, Wider H. Comparison of lead and sodium-cooled reactors - safety, fuel cycle performance, and some economical aspect. In: Proceedings of European nuclear conference, ENC2005, Versailles, France; 2005.
8. Abderrahim H.A., Kupschus P., Malambu E., et al. MYRRHA: a multipurpose accelerator driven system for research and development. Nucl Instrum Meth A 463 (2001) 487-494
9. Waters LS. MCNPX™ user's manual. Vers. 2.1.5, TPO-E83-G-UG-X00001; 1999.
10. Haeck W, Verboomen B. ALEPH-DLG 1.1.0 Creating cross-sections libraries for MCNP(X) and ALEPH, NEA/OECD, JEF/DOC-1125; 2006.
11. Barber DA et al. Final completion report for the coupled RELAP5/PARCS code, Technical Report, PU/NE-98-31, Purdue University; 1998.
12. Arien B et al., SITHER: a module for steady and unsteady thermal-hydraulic calculations in single fuel rod channels, internal report 63-151/80-88, Mol, SCK-CEN; 1980.
13. FUTURE, FUels for Transmutation of TransURanium Elements, Contract FIKI-CT-2001-00148, 5th Framework Programme EU; 2001.
14. Maschek W, Chen X, Delage F, et al. Accelerator driven systems for transmutation: fuel development, design and safety. In: The 2nd COE-INES international symposium on innovative nuclear energy systems, INES-2, November 26-30, 2006, Yokohama, Japan; 2006.
15. EUROTRANS, EUROpean Research Programme for the TRANSmutation of high level nuclear waste in an accelerator driven system, EU Contract FI6W-CT-2004-516520; 2006.
16. Maschek W., Rineiski A., Flad M., et al. Analysis of severe accident scenarios and proposals for safety improvements for ads transmuters with dedicated fuel. Nucl Technol 141 2 (2003)
17. Wang S, Flad M, Maschek W, Bandini G, Morita K, Analyses on SGTR transients and steam explosion potentials in EFIT. In: 2nd COE-INES (INES-2) international symposium on innovative nuclear energy systems, Yokohama, November 26-30; 2006.
18. Kondo Sa et al. SIMMER-III, a computer program for LMFR core disruptive accident analysis, Japan Nuclear Cycle Development Institute Report, JNC TN9400 2000-002; 2000.
19. Maschek W, Rineiski A, Suzuki TS, et al. SIMMER-III and SIMMER-IV safety code development for reactors with transmutation capability. In: Proceedings of M&C 2005 international conference, Avignon, France, September 12-15; 2005.
20. Briesmeister JF, MCNP-A gen. Monte-Carlo N-particle transport code, Version 4C, LA-13709-M; 2000.
21. Rimpault G et al. The ERANOS code and data system for fast reactor neutronic analyses. In: Proceedings of the International Conference of the new frontiers of nuclear technology: reactor physics, safety and high-performance computing (PHYSOR 2002), Seoul, Korea, October 7-10; 2002.
22. Alcouffe RE, Baker RS, Brinkley FW, et al. DANTSYS: a diffusion accelerated neutral particle transport code system, LA-12969-M; 1995.
23. Rineiski A et al. Kinetics and cross-section developments for analyses of reactor transmutation concepts with SIMMER, M&C 2005, September 12-15, Avignon, France; 2005.
24. Vergnes J., et al. The AMSTER concept. Nucl Eng Des 216 1 (2002) 43
25. MOST PROJECT, review and revaluation of molten salt reactor technology. and previous realisations or projects. In: 5th Framework programme of European Commission, EU Contract No. FIKW-CT-2001-00096; 2001.
26. Schikorr W.M. Assessment of the kinetic and dynamic transient behavior of sub-critical systems (ADS) in comparison to critical reactor systems. Nucl Eng Des 210 (2001) 95-123
27. Dulla S et al. Mathematical and numerical aspects in the kinetics of fluid fuel reactors. In: Proceedings of the 17th IMACS world congress scientific computation, applied mathematics and simulation, Paris, France, July 11-15; 2005.
28. Sanchez R., Mondot J., Stankovski Z., et al. APOLLO2: a user-oriented. Portable, modular code for multi-group transport calculations. Nucl Sci Eng 100 (1988) 352
29. Newton TD, Hutton JL. The next generation WIMS lattice code: WIMS9, Physor 2002, Seoul, Korean, October; 2002.
30. Ignatiev V et al. MOSART fuels and container materials study: case for Na, Li, Be/F solvent system. In: Proceedings of the GLOBAL 2003 (ANS/ENS International Winter Meeting), New Orleans, LA, USA, November 16-20; 2003.
31. Ignatiev V, Afonichkin V, Feynberg O, et al. Progress in integrated study of molten salt actinide recycler and transmuter system, actinide and fission product partitioning and transmutation, ninth information exchange meeting, Nîmes, France, 25-29 September; 2006.
32. Greene NM, Petrie LM. XSDRNPM: a one-dimensional discrete-ordinates code for transport analysis, Oak Ridge National Laboratory, NUREG/CR-0200 Volume 2, Section F3; 2000.
33. Gomin EA, Maiorov LV. The MCU Monte-Carlo code for 3-D depletion calculation, M&C 1999, Madrid, Spain; 1999.
34. Wang S, Rineiski A, Maschek W, Ignatiev V. Transient analyses for a molten salt transmutation reactor using the extended SIMMER-III code. In: Proceedings of ICONE 14 international conference on nuclear engineering, Miami, Florida, USA, July 17-20; 2006.
35. Dulla S, Ravetto P. Analysis of the role of fluid-dynamic phenomena in the neutronics of molten-salt systems, M&C 2005, September 12-15, Avignon, France; 2005.
36. MOST PROJECT, Review and revaluation of molten salt reactor technics and previous realisations or projects, 5th Framework Programme of European Commission, EU Contract No. FIKW-CT-2001-00096; 2001.
37. Uhlíř J, Souček P, Modolo G, Walle E, Nannicini R. EC/EURATOM report of the FP5 project MOST, FIKWT-CT-2001-00096, 08/2003 MOST-D7F; 2003.
38. Both JP, Lee Y, Mazzolo A, Peneliau Y, Petit O, Roesslinger B, Soldevila MA. Three-dimensional polykinetic particle transport Monte-Carlo code. In: International conference on supercomputing in nuclear applications; 2003.
39. Hendricks JS, MCNP4C3 - 3/22/01, Report X-5:RN(U)-JSH-01-17, Los Alamos National Laboratory, 13 April; 2001.
40. Oppe J, Kuijper JC. OCTOPUS_TNG Reference Guide, NRG Report 20748/03.54103/C, November; 2004.
41. Wu Y., Qian J.P., and Yu J.N. The fusion-driven hybrid system and its material selection. J Nucl Mater 307-311 Pt. 2 (2002) 1629-1636
42. Wu Y., Zheng S., Zhu X., Wang W., Wang H., Liu S., et al. Conceptual design of the fusion-driven subcritical system FDS-I. Fusion Eng Des 81 (2006) 1305-1311
43. Taczanowski S. Transmutations of nuclear waste in accelerator-driven subcritical systems. Appl Energy 75 (2003) 97-117
44. Taczanowski S., Cetnar J., and Domańska G. Fusion-driven transmutations of nuclear waste - a misconception or an incentive for promotion of fusion energy?. Fusion Eng Des 41 (1998) 455-460