-
1
-
-
17544385110
-
MYRRHA: a multipurpose accelerator driven system for research and development
-
Abderrahim H.A., et al. MYRRHA: a multipurpose accelerator driven system for research and development. Nuclear Instrumentation and Methods in Physics Research A 463 3 (2001) 487-494
-
(2001)
Nuclear Instrumentation and Methods in Physics Research A
, vol.463
, Issue.3
, pp. 487-494
-
-
Abderrahim, H.A.1
-
2
-
-
39549109682
-
-
Adamov E.O. and Orlov V.V., (1999), Nuclear development on the basis of new concepts of nuclear reactors and fuel cycle, Proceedings of Heavy Liquid Metal Coolants in Nuclear Technology (HLMC-98), Obninsk: SSC RF - IPPE, vol. 1, 24-31, (and references therein).
-
Adamov E.O. and Orlov V.V., (1999), Nuclear development on the basis of new concepts of nuclear reactors and fuel cycle, Proceedings of Heavy Liquid Metal Coolants in Nuclear Technology (HLMC-98), Obninsk: SSC RF - IPPE, vol. 1, 24-31, (and references therein).
-
-
-
-
3
-
-
39549118256
-
-
Adamov, E.O., Orlov, V.V., (Eds.), 2001. Naturally Safe Lead-Cooled Fast Reactor for Large-Scale Nuclear Power. Moscow.
-
Adamov, E.O., Orlov, V.V., (Eds.), 2001. Naturally Safe Lead-Cooled Fast Reactor for Large-Scale Nuclear Power. Moscow.
-
-
-
-
4
-
-
0017417473
-
Some observations on the compatibility of structural materials with molten lead
-
Asher R.C., Davies D., and Beetham S.A. Some observations on the compatibility of structural materials with molten lead. Corrosion Science 17 (1977) 545-557
-
(1977)
Corrosion Science
, vol.17
, pp. 545-557
-
-
Asher, R.C.1
Davies, D.2
Beetham, S.A.3
-
5
-
-
16444375905
-
Liquid metal embrittlement susceptibility of T91 steel by lead-bismuth
-
Auger T., and Lorang G. Liquid metal embrittlement susceptibility of T91 steel by lead-bismuth. Scripta Materialia 52 (2005) 1323-1328
-
(2005)
Scripta Materialia
, vol.52
, pp. 1323-1328
-
-
Auger, T.1
Lorang, G.2
-
6
-
-
5644232381
-
An overview of corrosion issues for the design and operation of high-temperature lead- and lead-bismuth-cooled reactor systems
-
Ballinger R., and Lim J. An overview of corrosion issues for the design and operation of high-temperature lead- and lead-bismuth-cooled reactor systems. Nuclear Technology 147 3 (2004) 418-435
-
(2004)
Nuclear Technology
, vol.147
, Issue.3
, pp. 418-435
-
-
Ballinger, R.1
Lim, J.2
-
7
-
-
0035397032
-
MEGAPIE: a 1 MW pilot experiment for a liquid metal spallation target
-
Bauer G.S., Salvatores M., and Heusener G. MEGAPIE: a 1 MW pilot experiment for a liquid metal spallation target. Journal of Nuclear Materials 296 (2001) 17-33
-
(2001)
Journal of Nuclear Materials
, vol.296
, pp. 17-33
-
-
Bauer, G.S.1
Salvatores, M.2
Heusener, G.3
-
8
-
-
39549113564
-
-
Blochin, V.A., et al., 1999. Experience of development and operation of oxide electrolytic sensors in lead-bismuth coolants. In: Proceedings of Heavy Liquid Metal Coolants in Nuclear Technology (HLMC-98), Obnisk, Russia, 588-592.
-
Blochin, V.A., et al., 1999. Experience of development and operation of oxide electrolytic sensors in lead-bismuth coolants. In: Proceedings of Heavy Liquid Metal Coolants in Nuclear Technology (HLMC-98), Obnisk, Russia, 588-592.
-
-
-
-
9
-
-
0020848303
-
Experimental studies on the use of liquid lead in a molten salt nuclear reactor
-
Broc M., Sannier J., and Santarini G. Experimental studies on the use of liquid lead in a molten salt nuclear reactor. Nuclear Technology 63 (1983) 197-208
-
(1983)
Nuclear Technology
, vol.63
, pp. 197-208
-
-
Broc, M.1
Sannier, J.2
Santarini, G.3
-
10
-
-
39549119017
-
-
Browne, J.C., Venneri, F., Li, N., Williamson, M., 1997. Accelerator-driven transmutation of waste, LANL White Paper, LA-UR-97-958.
-
Browne, J.C., Venneri, F., Li, N., Williamson, M., 1997. Accelerator-driven transmutation of waste, LANL White Paper, LA-UR-97-958.
-
-
-
-
11
-
-
7544222956
-
Electrochemical oxygen sensors for on-line monitoring in lead-bismuth alloys: status of development
-
(Special issue)
-
Courouau J.L. Electrochemical oxygen sensors for on-line monitoring in lead-bismuth alloys: status of development. Journal of Nuclear Materials 335 2 (2004) 254-259 (Special issue)
-
(2004)
Journal of Nuclear Materials
, vol.335
, Issue.2
, pp. 254-259
-
-
Courouau, J.L.1
-
12
-
-
0037839059
-
Mechanical properties of modified 9Cr-1Mo (T91) irradiated at <=300 °C in SINQ Target-3
-
Dai Y., et al. Mechanical properties of modified 9Cr-1Mo (T91) irradiated at <=300 °C in SINQ Target-3. Journal of Nuclear Materials 318 Suppl. (2003) 192-199
-
(2003)
Journal of Nuclear Materials
, vol.318
, Issue.SUPPL
, pp. 192-199
-
-
Dai, Y.1
-
13
-
-
39549123297
-
-
Darling, T. et al., 2001. Oxygen concentration measurement in liquid Pb-Bi eutectic. In: Proceedings of AccApp-ADTTA'01, Reno, Nevada.
-
Darling, T. et al., 2001. Oxygen concentration measurement in liquid Pb-Bi eutectic. In: Proceedings of AccApp-ADTTA'01, Reno, Nevada.
-
-
-
-
14
-
-
7544250467
-
Corrosion behavior of aluminized martensitic and austenitic steels liquid Pb-Bi
-
Deloffre P.H., et al. Corrosion behavior of aluminized martensitic and austenitic steels liquid Pb-Bi. Journal of Nuclear Materials 576 (2004) 180-184
-
(2004)
Journal of Nuclear Materials
, vol.576
, pp. 180-184
-
-
Deloffre, P.H.1
-
15
-
-
39549102092
-
-
th Framework Program.
-
th Framework Program.
-
-
-
-
16
-
-
39549110516
-
-
th FP CT-516520 (FI6W).
-
th FP CT-516520 (FI6W).
-
-
-
-
17
-
-
39549118255
-
-
Fazio C., et al. (Ed), The WPFC Working Group on LBE Technology contribution to the HLM handbook
-
In: Fazio C., et al. (Ed). Chapter XI: Existing HLM Facilities for Experimental Applications (2004), The WPFC Working Group on LBE Technology contribution to the HLM handbook
-
(2004)
Chapter XI: Existing HLM Facilities for Experimental Applications
-
-
-
19
-
-
0001053140
-
Use of lead-bismuth coolant in nuclear reactors and Accelerator-Driven Systems
-
Gromov B.F., et al. Use of lead-bismuth coolant in nuclear reactors and Accelerator-Driven Systems. Nuclear Engineering and Design 173 (1997) 207-217
-
(1997)
Nuclear Engineering and Design
, vol.173
, pp. 207-217
-
-
Gromov, B.F.1
-
20
-
-
39549107463
-
-
Grötzbach G. et al., 2004. Low Prandtl Number Thermalhydraulics (A Small Review of the Status and Open Issues), Presentation in the 2nd Meeting of the WPFC Working Group on LBE Technology, Paris, France.
-
Grötzbach G. et al., 2004. Low Prandtl Number Thermalhydraulics (A Small Review of the Status and Open Issues), Presentation in the 2nd Meeting of the WPFC Working Group on LBE Technology, Paris, France.
-
-
-
-
21
-
-
0035426225
-
A kinetic model for corrosion and precipitation in non-isothermal LBE flow loop
-
He X.Y., Mineev M., and Li N. A kinetic model for corrosion and precipitation in non-isothermal LBE flow loop. Journal of Nuclear Materials 297 (2001) 214-219
-
(2001)
Journal of Nuclear Materials
, vol.297
, pp. 214-219
-
-
He, X.Y.1
Mineev, M.2
Li, N.3
-
22
-
-
0034505507
-
The concept of proliferation-resistant, environment-friendly, accident-tolerant, continual and economical reactor (PEACER)
-
Hwang I.S., et al. The concept of proliferation-resistant, environment-friendly, accident-tolerant, continual and economical reactor (PEACER). Progress in Nuclear Energy 37 (2000) 217-222
-
(2000)
Progress in Nuclear Energy
, vol.37
, pp. 217-222
-
-
Hwang, I.S.1
-
23
-
-
39549123528
-
-
IAEA, 2002. Comparative assessment of thermophysical and thermohyraulic characteristics of lead, lead-bismuth and sodium coolants for fast reactors. IAEA-TECDOC-1289.
-
IAEA, 2002. Comparative assessment of thermophysical and thermohyraulic characteristics of lead, lead-bismuth and sodium coolants for fast reactors. IAEA-TECDOC-1289.
-
-
-
-
24
-
-
39549115791
-
-
IAEA, 2006. Theoretical and experimental studies of heavy liquid metal thermal hydraulics. In: Proceedings of a technical meeting held in Karlsruhe, Germany, 28-31 October 2003, IAEA-TECDOC-1520.
-
IAEA, 2006. Theoretical and experimental studies of heavy liquid metal thermal hydraulics. In: Proceedings of a technical meeting held in Karlsruhe, Germany, 28-31 October 2003, IAEA-TECDOC-1520.
-
-
-
-
25
-
-
0038624015
-
LiSoR, a liquid metal loop for material investigation under irradiation
-
Kirchner T., et al. LiSoR, a liquid metal loop for material investigation under irradiation. Journal of Nuclear Materials 318 Suppl. (2003) 70-83
-
(2003)
Journal of Nuclear Materials
, vol.318
, Issue.SUPPL
, pp. 70-83
-
-
Kirchner, T.1
-
27
-
-
0035397033
-
Development of oxygen meters for the use in lead-bismuth
-
Konys J., et al. Development of oxygen meters for the use in lead-bismuth. Journal of Nuclear Materials 296 (2001) 289-294
-
(2001)
Journal of Nuclear Materials
, vol.296
, pp. 289-294
-
-
Konys, J.1
-
28
-
-
0036134407
-
Active control of oxygen in molten lead-bismuth eutectic systems to prevent steel corrosion and coolant contamination
-
Li N. Active control of oxygen in molten lead-bismuth eutectic systems to prevent steel corrosion and coolant contamination. Journal of Nuclear Materials 300 (2002) 73-81
-
(2002)
Journal of Nuclear Materials
, vol.300
, pp. 73-81
-
-
Li, N.1
-
29
-
-
9544247738
-
The influence of proton irradiation on the corrosion of HT-9 during immersion in lead bismuth eutectic
-
Lillard S., et al. The influence of proton irradiation on the corrosion of HT-9 during immersion in lead bismuth eutectic. Journal of Nuclear Materials 335 3 (2004) 487-492
-
(2004)
Journal of Nuclear Materials
, vol.335
, Issue.3
, pp. 487-492
-
-
Lillard, S.1
-
30
-
-
39549111784
-
-
Los Alamos National Laboratory, 2003. AAA Materials Handbook - Materials Data for Particle Accelerator Applications. revision 4 (LA-CP-03-0868).
-
Los Alamos National Laboratory, 2003. AAA Materials Handbook - Materials Data for Particle Accelerator Applications. revision 4 (LA-CP-03-0868).
-
-
-
-
32
-
-
39549121371
-
-
MEGAPIE-TEST - Megawatt Pilot Experiment - Test, EC 5th FP FIKW-CT-2001-00159; and Cadiou, A., et al., 2004. MEGAPIE-TEST: Final Summary Report on Target Design.
-
MEGAPIE-TEST - Megawatt Pilot Experiment - Test, EC 5th FP FIKW-CT-2001-00159; and Cadiou, A., et al., 2004. MEGAPIE-TEST: Final Summary Report on Target Design.
-
-
-
-
33
-
-
39549090759
-
OMEGA programme in Japan and ADS development at JAERI
-
Mukaiyama T. OMEGA programme in Japan and ADS development at JAERI. IAEA-TECDOC 1365 (1999) 153-165
-
(1999)
IAEA-TECDOC
, vol.1365
, pp. 153-165
-
-
Mukaiyama, T.1
-
34
-
-
7544241996
-
Behavior of steels in flowing liquid PbBi eutectic alloy at 420-600 °C after 4000-7200 h
-
Muller G., et al. Behavior of steels in flowing liquid PbBi eutectic alloy at 420-600 °C after 4000-7200 h. Journal of Nuclear Materials 335 2 (2004) 163-168
-
(2004)
Journal of Nuclear Materials
, vol.335
, Issue.2
, pp. 163-168
-
-
Muller, G.1
-
36
-
-
34248572447
-
Effects of oxygen on fouling behavior in lead-bismuth coolant systems
-
Niu F., Candalino R., and Li N. Effects of oxygen on fouling behavior in lead-bismuth coolant systems. Journal of Nuclear Materials 366 (2007) 216-222
-
(2007)
Journal of Nuclear Materials
, vol.366
, pp. 216-222
-
-
Niu, F.1
Candalino, R.2
Li, N.3
-
37
-
-
39549109595
-
A review of research and development on accelerator-driven system for transmutation of long-lived nuclear waste at JAERI
-
IAEA, Vienna
-
Oigawa H. A review of research and development on accelerator-driven system for transmutation of long-lived nuclear waste at JAERI. 37th Meeting of IAEA Technical Working Group on Fast Reactors and ADS (2004), IAEA, Vienna
-
(2004)
37th Meeting of IAEA Technical Working Group on Fast Reactors and ADS
-
-
Oigawa, H.1
-
38
-
-
39549092500
-
-
Orlov, Y.I., 1997. Stages of development of lead-bismuth as a coolant for nuclear reactors in Russia, In: International Workshop on Physics of Accelerator-Driven Systems for Nuclear Transmutation and Energy Production, Trento, Italy, September 29-October 3.
-
Orlov, Y.I., 1997. Stages of development of lead-bismuth as a coolant for nuclear reactors in Russia, In: International Workshop on Physics of Accelerator-Driven Systems for Nuclear Transmutation and Energy Production, Trento, Italy, September 29-October 3.
-
-
-
-
39
-
-
34249021441
-
-
Pankratov, D.V. et al., 2005. Analysis of polonium danger in nuclear power installations with lead-bismuth coolant. In: Proceedings of ICAPP'05, #5497, Seoul, Korea.
-
Pankratov, D.V. et al., 2005. Analysis of polonium danger in nuclear power installations with lead-bismuth coolant. In: Proceedings of ICAPP'05, #5497, Seoul, Korea.
-
-
-
-
40
-
-
39549109391
-
-
Park W.S. et al., 1996. Development of nuclear transmutation technology. KAERI/RR-1702/96.
-
Park W.S. et al., 1996. Development of nuclear transmutation technology. KAERI/RR-1702/96.
-
-
-
-
41
-
-
39549101874
-
-
Parkman, R., Shepard, O.C., 1951. Investigation of materials for use in a heat transfer system containing liquid lead alloys. Report No. XII, United States Atomic Energy Commission report, ORO-45.
-
Parkman, R., Shepard, O.C., 1951. Investigation of materials for use in a heat transfer system containing liquid lead alloys. Report No. XII, United States Atomic Energy Commission report, ORO-45.
-
-
-
-
42
-
-
0343005820
-
A high-gain energy amplifier operated with fast neutrons
-
Rubbia C. A high-gain energy amplifier operated with fast neutrons. Nuclear Instruments and Methods A 230 (1992) 336
-
(1992)
Nuclear Instruments and Methods A
, vol.230
, pp. 336
-
-
Rubbia, C.1
-
44
-
-
39549083774
-
-
SPIRE - irradiation effects in martensitic steels under neutron and proton mixed spectrum, 2000. EC 5th FP FIKW-CT-2000-00058.
-
SPIRE - irradiation effects in martensitic steels under neutron and proton mixed spectrum, 2000. EC 5th FP FIKW-CT-2000-00058.
-
-
-
-
46
-
-
39549119451
-
-
TECLA - Technologies, Materials, 2000. Thermal-Hydraulics for Lead Alloys. EC 5th Framework Program.
-
TECLA - Technologies, Materials, 2000. Thermal-Hydraulics for Lead Alloys. EC 5th Framework Program.
-
-
-
-
47
-
-
39549116628
-
-
United States Department of Energy, 1999. A Roadmap for Developing ATW Technology - A Report to Congress. US DOE/RW-0519.
-
United States Department of Energy, 1999. A Roadmap for Developing ATW Technology - A Report to Congress. US DOE/RW-0519.
-
-
-
-
49
-
-
0034299519
-
Disposition of nuclear waste using subcritical Accelerator-Driven Systems: technology choices and implementation scenarios
-
Venneri F., et al. Disposition of nuclear waste using subcritical Accelerator-Driven Systems: technology choices and implementation scenarios. Nuclear Technology 132 1 (2000) 15-29
-
(2000)
Nuclear Technology
, vol.132
, Issue.1
, pp. 15-29
-
-
Venneri, F.1
-
50
-
-
7544227541
-
Mechanical behavior of the T91 martensitic steel under monotonic and cyclic loadings in liquid metals
-
Voga J.B., et al. Mechanical behavior of the T91 martensitic steel under monotonic and cyclic loadings in liquid metals. Journal of Nuclear Materials 335 (2004) 222-226
-
(2004)
Journal of Nuclear Materials
, vol.335
, pp. 222-226
-
-
Voga, J.B.1
-
51
-
-
39549107004
-
-
Wade, D. et al., 2002. Secure transportable autonomous reactor for hydrogen production & desalination. In: Proceedings of ICONE-10.
-
Wade, D. et al., 2002. Secure transportable autonomous reactor for hydrogen production & desalination. In: Proceedings of ICONE-10.
-
-
-
-
52
-
-
0025991191
-
Mortality among a cohort of workers monitored for 210Po exposure: 1944-1972
-
Wiggs L.D., et al. Mortality among a cohort of workers monitored for 210Po exposure: 1944-1972. Health Physics 61 1 (1991) 71-76
-
(1991)
Health Physics
, vol.61
, Issue.1
, pp. 71-76
-
-
Wiggs, L.D.1
-
53
-
-
1442334927
-
Corrosion/precipitation in non-isothermal and multi-modular LBE loop
-
Zhang J., and Li N. Corrosion/precipitation in non-isothermal and multi-modular LBE loop. Journal of Nuclear Materials 326 (2004) 201-210
-
(2004)
Journal of Nuclear Materials
, vol.326
, pp. 201-210
-
-
Zhang, J.1
Li, N.2
-
54
-
-
39549090053
-
-
Zrodnikov, A.V. et al., 2000. Multi-purposed reactor module SVBR-75/100, ICONE-8072. In: Proceedings of the 8th International Conference on Nuclear Engineering, Baltimore, MD, USA.
-
Zrodnikov, A.V. et al., 2000. Multi-purposed reactor module SVBR-75/100, ICONE-8072. In: Proceedings of the 8th International Conference on Nuclear Engineering, Baltimore, MD, USA.
-
-
-
|