-
1
-
-
33751104293
-
-
Carluec, B., Anzieu, P., 1999. Proposal for a gas-cooled ADS demonstrator. In: Proc. Third Int. Conf. on Accelerator Driven Transmutation Technologies and Applications, ADTTA'99, Praha, Czech Republic, 7-11 June.
-
-
-
-
2
-
-
33751096536
-
-
Cetnar, J. et al., 1998. MCB: a continuous energy Monte-Carlo burnup simulation code. Actinide and Fission Product Partitioning and Transmutation. In: Proc. of the Fifth Int. Information Exchange Meeting Mol, Belgium.
-
-
-
-
3
-
-
33751075021
-
-
ENEA, 2001. A European Roadmap for Developing Accelerator Driven Systems (ADS) for Nuclear Waste Incineration, Technical Report, The European Technical Working Group on ADS, ISBN 88-8286-008-6.
-
-
-
-
4
-
-
0018157553
-
Peach bottom unit no. 1: a high performance helium cooled nuclear power plant
-
Everett III J.L., and Kohler E.J. Peach bottom unit no. 1: a high performance helium cooled nuclear power plant. Ann. Nucl. Energy 5 (1978) 321
-
(1978)
Ann. Nucl. Energy
, vol.5
, pp. 321
-
-
Everett III, J.L.1
Kohler, E.J.2
-
5
-
-
0037701712
-
-
Feldman, E.E., Wei, T.Y.C., 2003. Cold-finger concept for passive decay heat removal in gas-cooled reactors, In: ANS Annual Meeting, San Diego, USA, 1-5 June.
-
-
-
-
6
-
-
33751086536
-
-
Foster, D.G. (Ed.), 1974. Review of PNL study on transmutation processing of high level waste, LA-UR 74-74, Los Alamos National Laboratory.
-
-
-
-
7
-
-
84933182737
-
-
Gaillard, J.P. et al., 2003. Thermal-hydraulic design of a gas cooled fast reactor. In: 2003 International Congress on Advances in Nuclear Power Plants ICCAP'03, Córdoba, Spain, 4-7 May 2003.
-
-
-
-
8
-
-
0343063630
-
A gas-cooled fast reactor using coated particle fuel
-
Gratton C.P., et al. A gas-cooled fast reactor using coated particle fuel. J. Br. Nucl. Energy Soc. 7 (1968) 235
-
(1968)
J. Br. Nucl. Energy Soc.
, vol.7
, pp. 235
-
-
Gratton, C.P.1
-
9
-
-
0038347111
-
Minor actinides transmutation scenario studies with PWRs, FRs and moderated targets
-
Grouiller J.P., et al. Minor actinides transmutation scenario studies with PWRs, FRs and moderated targets. J. Nucl. Mater. 320 (2003) 163
-
(2003)
J. Nucl. Mater.
, vol.320
, pp. 163
-
-
Grouiller, J.P.1
-
10
-
-
27144549750
-
330-MW(e) Fort St. Vrain high-temperature gas-cooled reactor
-
Habush A.L., and Harris A.M. 330-MW(e) Fort St. Vrain high-temperature gas-cooled reactor. Nucl. Eng. Des. 7 (1968) 312
-
(1968)
Nucl. Eng. Des.
, vol.7
, pp. 312
-
-
Habush, A.L.1
Harris, A.M.2
-
11
-
-
0016579435
-
Mechanical properties of unirradiated fast reactor cladding during simulated overpower transients
-
Hunter C.W., et al. Mechanical properties of unirradiated fast reactor cladding during simulated overpower transients. Nucl. Technol. 27 3 (1975) 376
-
(1975)
Nucl. Technol.
, vol.27
, Issue.3
, pp. 376
-
-
Hunter, C.W.1
-
12
-
-
33751109548
-
-
IAEA, 2001. ENDF/B-VI Release 8, The US Evaluated Nuclear Data Library for Neutron Reaction Data, IAEA-NDS-100, Rev. 11.
-
-
-
-
13
-
-
33144487610
-
Calculating the effective delayed neutron fraction with Monte Carlo
-
Klein Muelekamp R., and van der Marck S. Calculating the effective delayed neutron fraction with Monte Carlo. Nucl. Sci. Eng. 152 (2006) 142-148
-
(2006)
Nucl. Sci. Eng.
, vol.152
, pp. 142-148
-
-
Klein Muelekamp, R.1
van der Marck, S.2
-
14
-
-
33751112823
-
-
Konomura, M. et al., 2003. A promising gas-cooled fast reactor and its R&D plan. In: International Conference on Future nuclear systems, GLOBAL 03, New Orleans, USA.
-
-
-
-
15
-
-
33751071671
-
-
Languille, A. et al., 1995. CAPRA core studies - the oxide reference option. In: International Conference on Future nuclear systems, GLOBAL 95, Versailles, France.
-
-
-
-
16
-
-
33751084405
-
-
Makaiyama, T., Gunji, Y., 1990. Characteristics of minor actinide transmutation in minor actinide burner reactors and power reactor. In: Proceedings of the First International Information Exchange Meeting on Actinide and Fission Product Separation and Transmutation, Mito, Japan.
-
-
-
-
17
-
-
33751072992
-
-
Melese-d'Hospital, G.B., 1980. Review of gas cooled reactors thermal hydraulics. In: Proc. ANS/ASME/NRC International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Saratoga Springs, USA, 5-8 October 1980.
-
-
-
-
18
-
-
33751092616
-
-
Naganuma, M. et al., 2002. Design study on core and fuel properties of helium gas cooled fast reactors (coated particle type fuel reactor/pin type fuel reactor) - Results in JFY2001 (in Japanese), JNC TN9400 2002-074.
-
-
-
-
19
-
-
33751081883
-
-
OECD/NEA, 1999. Status and Assessment Report on Actinide and Fission Product Partitioning and Transmutation, Paris.
-
-
-
-
20
-
-
33751092885
-
-
OECD/NEA, 2005. The JEFF-3.0 Nuclear Data Library, JEFF Report 19.
-
-
-
-
21
-
-
33751107015
-
-
Petti, D.A. et al., 2002. Key differences in the fabrication of US and German TRISO-coated particle fuel, and their implication on fuel performance. In: Proceedings of the Conference on High Temperature Reactors, Petten, April 22-24.
-
-
-
-
22
-
-
0018108297
-
Achievements of the Dragon project
-
Rennie C.A. Achievements of the Dragon project. Ann. Nucl. Energy 5 (1978) 305
-
(1978)
Ann. Nucl. Energy
, vol.5
, pp. 305
-
-
Rennie, C.A.1
-
23
-
-
33751105336
-
-
Sato, M. et al., 2003. Numerical study on plant dynamic characteristics of helium gas cooled fast reactor (in Japanese), JNC TN9400 2003-100.
-
-
-
-
24
-
-
0242408361
-
Definition and application of proton source efficiency in accelerator driven systems
-
Seltborg P., et al. Definition and application of proton source efficiency in accelerator driven systems. Nucl. Sci. Eng. 145 (2003) 390-399
-
(2003)
Nucl. Sci. Eng.
, vol.145
, pp. 390-399
-
-
Seltborg, P.1
-
25
-
-
33751118835
-
-
Taiwo, T.A. et al., 2002. Physics studies for a particle-bed gas cooled fast reactor core design. In: Proceedings of the Conference on High Temperature Reactors, HTR-2002, Petten, NL, April 22-24.
-
-
-
-
26
-
-
33751087291
-
-
Takizuka, T. et al., 1991. Conceptual design of transmutation plant. In: Specialist Mtg. on Accelerator-driven Transmutation Technology for Radwaste and other Applications, Stockholm 24-28 June.
-
-
-
-
27
-
-
33751091319
-
-
Takizuka, T. et al., 1998. Studies on accelerator-driven transmutation systems. Actinide and Fission Product Partitioning and Transmutation. In: Proceedings of the Fifth Int. Information Exchange Meeting, Mol, Belgium.
-
-
-
-
28
-
-
1542305431
-
Neutronics design for lead-bismuth cooled accelerator-driven system for transmutation of minor actinide
-
Tsujimoto K., et al. Neutronics design for lead-bismuth cooled accelerator-driven system for transmutation of minor actinide. J. Nucl. Sci. Technol. 41 1 (2004) 21
-
(2004)
J. Nucl. Sci. Technol.
, vol.41
, Issue.1
, pp. 21
-
-
Tsujimoto, K.1
-
29
-
-
33751111248
-
-
US DOE, 2003. Advanced fuel cycle initiative. Annual report 2003.
-
-
-
-
30
-
-
28044451522
-
Neutronics of minor actinide burning accelerator driven systems with ceramic fuel
-
Wallenius J., and Eriksson M. Neutronics of minor actinide burning accelerator driven systems with ceramic fuel. Nucl. Technol. 152 (2005) 367-381
-
(2005)
Nucl. Technol.
, vol.152
, pp. 367-381
-
-
Wallenius, J.1
Eriksson, M.2
-
31
-
-
33645918000
-
Neutronic and safety aspects of a gas-cooled subcritical core for minor actinide transmutation
-
Westlén D., and Wallenius J. Neutronic and safety aspects of a gas-cooled subcritical core for minor actinide transmutation. Nucl. Technol. 154 (2006) 41-51
-
(2006)
Nucl. Technol.
, vol.154
, pp. 41-51
-
-
Westlén, D.1
Wallenius, J.2
-
32
-
-
0032092342
-
Actinide transmutation properties of thermal and fast fission reactors including multiple recycling
-
Wiese H.W. Actinide transmutation properties of thermal and fast fission reactors including multiple recycling. J. Alloys Compd. 271 (1998) 522
-
(1998)
J. Alloys Compd.
, vol.271
, pp. 522
-
-
Wiese, H.W.1
-
33
-
-
0035426175
-
Blanket design studies of a lead-bismuth eutectic-cooled accelerator transmutation of waste system
-
Yang W.S., and Khalil H.S. Blanket design studies of a lead-bismuth eutectic-cooled accelerator transmutation of waste system. Nucl. Technol. 135 (2001) 162
-
(2001)
Nucl. Technol.
, vol.135
, pp. 162
-
-
Yang, W.S.1
Khalil, H.S.2
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