-
2
-
-
30544432674
-
Overview of the ARIES-AT advanced tokamak, advanced technology fusion power plant
-
F. Najmabadi and The ARIES Team, Overview of the ARIES-AT advanced tokamak, advanced technology fusion power plant, Fus. Eng. Des. 80 (2006) 3-23.
-
(2006)
Fus. Eng. Des.
, vol.80
, pp. 3-23
-
-
Najmabadi, F.1
-
4
-
-
30544444616
-
Nuclear performance assessment for ARIES-AT
-
L. El-Guebaly Nuclear performance assessment for ARIES-AT Fus. Eng. Des. 80 2006 99 110
-
(2006)
Fus. Eng. Des.
, vol.80
, pp. 99-110
-
-
El-Guebaly, L.1
-
5
-
-
0003776598
-
-
FENDL/MG-2.0 and FENDL/MC-2.0 Report IAEA-NDS-176, International Atomic Energy Agency, March
-
M. Herman, H. Wienke, FENDL/MG-2.0 and FENDL/MC-2.0, The Processed Cross-Section Libraries for Neutron-Photon Transport Calculations, Report IAEA-NDS-176, International Atomic Energy Agency, March 1997.
-
(1997)
The Processed Cross-section Libraries for Neutron-photon Transport Calculations
-
-
Herman, M.1
Wienke, H.2
-
6
-
-
0003542678
-
DANTSYS: A diffusion accelerated neutral particle transport code system
-
June
-
DANTSYS: A Diffusion Accelerated Neutral Particle Transport Code System, Los Alamos National Laboratory Report, LA-12969-M, June 1995.
-
(1995)
Los Alamos National Laboratory Report
, vol.LA-12969-M
-
-
-
7
-
-
0004217649
-
-
University of Wisconsin Fusion Technology Institute, UWFDM-1070, January
-
P. Wilson, D. Henderson, ALARA: Analytic and Laplacian Adaptive Radioactivity Analysis Code Technical Manual, University of Wisconsin Fusion Technology Institute, UWFDM-1070, January 1998, http://legacy.ep.wisc.edu/∼wilsonp/projects/ALARA/users.guide.html/.
-
(1998)
ALARA: Analytic and Laplacian Adaptive Radioactivity Analysis Code Technical Manual
-
-
Wilson, P.1
Henderson, D.2
-
8
-
-
0003624268
-
Neutron activation cross-section data library for fusion applications
-
FENDL/A-2.0
-
A. Pashchenko, H. Wienke, J. Kopecky, et al., FENDL/A-2.0, neutron activation cross-section data library for fusion applications, International Atomic Energy Agency Report, IAEA-NDS-173, 1998.
-
(1998)
International Atomic Energy Agency Report
, vol.IAEA-NDS-173
-
-
Pashchenko, A.1
Wienke, H.2
Kopecky, J.3
-
9
-
-
30544440160
-
Advanced power core system for the ARIES-AT power plant
-
A.R. Raffray, L. El-Guebaly, S. Malang, I. Sviatoslavsky, M.S. Tillack, X. Wang and The ARIES Team, Advanced power core system for the ARIES-AT power plant, Fus. Eng. Des. 80 (2006) 79-98.
-
(2006)
Fus. Eng. Des.
, vol.80
, pp. 79-98
-
-
Raffray, A.R.1
El-Guebaly, L.2
Malang, S.3
Sviatoslavsky, I.4
Tillack, M.S.5
Wang, X.6
-
12
-
-
0029273163
-
Comparison of lithium and the eutectic lead-lithium alloy, two candidate liquid metal breeder materials for self-cooled blankets
-
S. Malang, and R. Mattas Comparison of lithium and the eutectic lead-lithium alloy, two candidate liquid metal breeder materials for self-cooled blankets Fus. Eng. Des. 27 1995 399 406
-
(1995)
Fus. Eng. Des.
, vol.27
, pp. 399-406
-
-
Malang, S.1
Mattas, R.2
-
14
-
-
0003524558
-
-
S 81 RI 19 97-05-04 W1.1, SEHD 8.1.C-1, May 6
-
H.-W. Bartels (Ed.), Accident Analysis Specifications for NSSR-2 (AAS), Version 2, S 81 RI 19 97-05-04 W1.1, SEHD 8.1.C-1, May 6, 1997.
-
(1997)
Accident Analysis Specifications for NSSR-2 (AAS), Version 2
-
-
Bartels, H.-W.1
-
15
-
-
0030074126
-
Effect of breach area and length to exchange flow rates under the LOVA condition in a fusion reactor
-
K. Takase, T. Kunugi, and Y. Seki Effect of breach area and length to exchange flow rates under the LOVA condition in a fusion reactor Fus. Technol. 30 December 1996
-
(1996)
Fus. Technol.
, vol.30
-
-
Takase, K.1
Kunugi, T.2
Seki, Y.3
-
16
-
-
0003617572
-
-
NUREG/CR-5531, SAND90-0364, Sandia National Laboratories, Albuquerque, NM, January
-
R.M. Summers, R.K. Cole Jr., E.A. Boucheron, M.K. Carmel, S.E. Dingman, J.E. Kelly, MELCOR 1.8.0: A Computer Code for Nuclear Reactor Severe Accident Source Term and Risk Assessment Analyses, NUREG/CR-5531, SAND90-0364, Sandia National Laboratories, Albuquerque, NM, January 1991.
-
(1991)
MELCOR 1.8.0: A Computer Code for Nuclear Reactor Severe Accident Source Term and Risk Assessment Analyses
-
-
Summers, R.M.1
Cole Jr., R.K.2
Boucheron, E.A.3
Carmel, M.K.4
Dingman, S.E.5
Kelly, J.E.6
-
17
-
-
18344415609
-
Modifications to the MELCOR code for application in fusion accident analyses
-
B.J. Merrill, R.L. Moore, S.T. Polkinghorne, and D.A. Petti Modifications to the MELCOR code for application in fusion accident analyses Fus. Eng. Des. 51-52 2000 555 563
-
(2000)
Fus. Eng. Des.
, vol.51-52
, pp. 555-563
-
-
Merrill, B.J.1
Moore, R.L.2
Polkinghorne, S.T.3
Petti, D.A.4
-
19
-
-
0021413673
-
Physical properties and chemical reaction behavior of Li17Pb83 related to its use as a fusion reactor blanket material
-
G. Kuhlborsch, and F. Reiger Physical properties and chemical reaction behavior of Li17Pb83 related to its use as a fusion reactor blanket material Nucl. Eng. Des./Fus. 1 1984 195 203
-
(1984)
Nucl. Eng. Des./Fus.
, vol.1
, pp. 195-203
-
-
Kuhlborsch, G.1
Reiger, F.2
-
20
-
-
0042453188
-
Lithium alloy chemical reactivity with reactor materials: Current state of knowledge
-
M. Corradini, and D.W. Jeppson Lithium alloy chemical reactivity with reactor materials: current state of knowledge Fus. Eng. Des. 14 1991 273 288
-
(1991)
Fus. Eng. Des.
, vol.14
, pp. 273-288
-
-
Corradini, M.1
Jeppson, D.W.2
-
21
-
-
0035312057
-
A lithium-air reaction model for the MELCOR code for analyzing lithium fires in fusion reactors
-
B.J. Merrill A lithium-air reaction model for the MELCOR code for analyzing lithium fires in fusion reactors Fus. Eng. Des. 54 2001 485 493
-
(2001)
Fus. Eng. Des.
, vol.54
, pp. 485-493
-
-
Merrill, B.J.1
-
25
-
-
0034318548
-
Re-evaluation of the use of low activation materials in waste management strategies for fusion
-
D.A. Petti, K.A. McCarthy, N.P. Taylor, C.B.A. Forty, and R.A. Forrest Re-evaluation of the use of low activation materials in waste management strategies for fusion Fus. Eng. Des. 51-52 2000 435 444
-
(2000)
Fus. Eng. Des.
, vol.5152
, pp. 435-444
-
-
Petti, D.A.1
McCarthy, K.A.2
Taylor, N.P.3
Forty, C.B.A.4
Forrest, R.A.5
-
30
-
-
0342627788
-
Clearance levels for radionuclides in solid materials - Application of exemption principles
-
IAEA-TECDOC-855
-
IAEA, Clearance Levels for Radionuclides in Solid Materials - Application of Exemption Principles, Interim Report for Comment, IAEA-TECDOC-855, 1996.
-
(1996)
Interim Report for Comment
-
-
|