-
1
-
-
0141818957
-
The burnup capabilities of the deep burn modular helium reactor analyzed by the Monte Carlo continuous energy code MCB
-
A. TALAMO, W. GUDOWSKI, and F. VENNERI, "The Burnup Capabilities of the Deep Burn Modular Helium Reactor Analyzed by the Monte Carlo Continuous Energy Code MCB," Ann. Nucl. Energy, 31, 2, 173 (2004).
-
(2004)
Ann. Nucl. Energy
, vol.31
, Issue.2
, pp. 173
-
-
Talamo, A.1
Gudowski, W.2
Venneri, F.3
-
2
-
-
4444238018
-
Key physical parameters and temperature reactivity coefficients of the deep burn modular helium reactor fueled with LWRs waste
-
A. TALAMO, W. GUDOWSKI, J. CETNAR, and F. VENNERI, "Key Physical Parameters and Temperature Reactivity Coefficients of the Deep Burn Modular Helium Reactor Fueled with LWRs Waste,"Ann. Nucl. Energy, 31, 16, 1913 (2004).
-
(2004)
Ann. Nucl. Energy
, vol.31
, Issue.16
, pp. 1913
-
-
Talamo, A.1
Gudowski, W.2
Cetnar, J.3
Venneri, F.4
-
3
-
-
13244277620
-
Comparative studies of ENDF/B-6.8, JEF-2.2 and JENDL-3.2 data libraries by Monte Carlo modeling of high temperature reactors on plutonium based fuel cycles
-
A. TALAMO and W. GUDOWSKI, "Comparative Studies of ENDF/B-6.8, JEF-2.2 and JENDL-3.2 Data Libraries by Monte Carlo Modeling of High Temperature Reactors on Plutonium Based Fuel Cycles," J. Nucl. Sci. Technol., 41, 12, 1228 (2004).
-
(2004)
J. Nucl. Sci. Technol.
, vol.41
, Issue.12
, pp. 1228
-
-
Talamo, A.1
Gudowski, W.2
-
4
-
-
22344434427
-
GT-MHR conceptual design description report
-
GA/NRC-337-02
-
"GT-MHR Conceptual Design Description Report," GA/NRC-337-02, General Atomics (2002).
-
(2002)
General Atomics
-
-
-
5
-
-
0038414939
-
Deep-burn: Making nuclear waste transmutation practical
-
C. RODRIGUEZ, A. BAXTER, D. MCEACHERN, M. FIKANI, and F. VENNERI, "Deep-Burn: Making Nuclear Waste Transmutation Practical," Nucl. Eng. Des., 222, 299 (2003).
-
(2003)
Nucl. Eng. Des.
, vol.222
, pp. 299
-
-
Rodriguez, C.1
Baxter, A.2
Mceachern, D.3
Fikani, M.4
Venneri, F.5
-
6
-
-
0037738848
-
Neutronic features of the GT-MHR
-
N. KODOCHIGOV et al., "Neutronic Features of the GT-MHR," Nucl. Eng. Des., 222, 161 (2003).
-
(2003)
Nucl. Eng. Des.
, vol.222
, pp. 161
-
-
Kodochigov, N.1
-
7
-
-
0038685913
-
Modelling of HTRs with Monte Carlo: From a homogeneous to an exact heterogeneous core with microparticles, Ann
-
R. PLUKIENE and D. RIDIKAS, "Modelling of HTRs with Monte Carlo: From a Homogeneous to an Exact Heterogeneous Core with Microparticles," Ann. Nucl. Energy, 30, 1573 (2003).
-
(2003)
Nucl. Energy
, vol.30
, pp. 1573
-
-
Plukiene, R.1
Ridikas, D.2
-
8
-
-
0141573603
-
Reactor-based transmutation - Physics studies of the gas-cooled graphite-moderated deep burn reactor, GA-501-0-TRT-000140
-
A. BAXTER and M. FIKANI, "Reactor-Based Transmutation - Physics Studies of the Gas-Cooled Graphite-Moderated Deep Burn Reactor," GA-501-0-TRT-000140, General Atomics (2002).
-
(2002)
General Atomics
-
-
Baxter, A.1
Fikani, M.2
-
9
-
-
0034795735
-
The application of gas-cooled reactor technologies to the transmutation of nuclear waste
-
A. BAXTER and C. RODRIGUEZ, "The Application of Gas-Cooled Reactor Technologies to the Transmutation of Nuclear Waste," Prog. Nucl. Energy, 38, 81 (2001).
-
(2001)
Prog. Nucl. Energy
, vol.38
, pp. 81
-
-
Baxter, A.1
Rodriguez, C.2
-
10
-
-
0034503578
-
Modular high temperature reactor contributing the global environmental protection
-
K. OHASHI, F. OKAMOTO, and H. HAYAKAWA, "Modular High Temperature Reactor Contributing the Global Environmental Protection," Prog. Nucl. Energy, 37, 307 (2000).
-
(2000)
Prog. Nucl. Energy
, vol.37
, pp. 307
-
-
Ohashi, K.1
Okamoto, F.2
Hayakawa, H.3
-
11
-
-
0034503892
-
Desirability of small reactors, HTGR in particular
-
Y. TSUCHIE, "Desirability of Small Reactors, HTGR in Particular," Prog. Nucl. Energy, 37, 253 (2000).
-
(2000)
Prog. Nucl. Energy
, vol.37
, pp. 253
-
-
Tsuchie, Y.1
-
12
-
-
0000027602
-
Project of the GT-MHR high temperature helium reactor with gas turbine
-
A. I. KIRYUSHIN et al., "Project of the GT-MHR High Temperature Helium Reactor with Gas Turbine," Nucl. Eng. Des., 173, 119 (1997).
-
(1997)
Nucl. Eng. Des.
, vol.173
, pp. 119
-
-
Kiryushin, A.I.1
-
13
-
-
4444367371
-
Where does the GT-MHR go from here?
-
J. D. WISTROM and W. A. SIMON, "Where Does the GT-MHR Go from Here?" Nucl. Eng. Int., 41, 10 (1996).
-
(1996)
Nucl. Eng. Int.
, vol.41
, pp. 10
-
-
Wistrom, J.D.1
Simon, W.A.2
-
14
-
-
27144527418
-
Comparative economics of the GT-MHR and power generation alternatives
-
GA-A 21722
-
M. P. LABAR and W. A. SIMON, "Comparative Economics of the GT-MHR and Power Generation Alternatives," GA-A 21722, General Atomics (1994).
-
(1994)
General Atomics
-
-
Labar, M.P.1
Simon, W.A.2
-
15
-
-
34547415910
-
Studies of air ingress for pebble bed reactors
-
Petten, The Netherlands, April 22-24, 2002, International Atomic Energy Agency
-
R. L. MOORE, C. H. OH, B. J. MERRILL, and D. A. PETTI, "Studies of Air Ingress for Pebble Bed Reactors," Proc. 1st Int. Topl. Mtg. High Temperature Reactor Technology, Petten, The Netherlands, April 22-24, 2002, International Atomic Energy Agency (2002).
-
(2002)
Proc. 1st Int. Topl. Mtg. High Temperature Reactor Technology
-
-
Moore, R.L.1
Oh, C.H.2
Merrill, B.J.3
Petti, D.A.4
-
16
-
-
33745574131
-
Calculation of the decay heat removal transient by passive means for a direct cycle modular HTR
-
Petten, The Netherlands, April 22-24, 2002, International Atomic Energy Agency
-
A. WOAYE-HUNE and S. EHSTER, "Calculation of the Decay Heat Removal Transient by Passive Means for a Direct Cycle Modular HTR," Proc. 1st Int. Topl. Mtg. High Temperature Reactor Technology, Petten, The Netherlands, April 22-24, 2002, International Atomic Energy Agency (2002).
-
(2002)
Proc. 1st Int. Topl. Mtg. High Temperature Reactor Technology
-
-
Woaye-Hune, A.1
Ehster, S.2
-
17
-
-
0035251490
-
Development of a simulation model and safety evaluation for a depressurization accident without reactor scram in an advanced HTGR
-
S. NAKAGAWA, A. SAIKUSA, and K. KUNTTOMI, "Development of a Simulation Model and Safety Evaluation for a Depressurization Accident Without Reactor Scram in an Advanced HTGR," Nucl. Technol., 133, 141 (2001).
-
(2001)
Nucl. Technol.
, vol.133
, pp. 141
-
-
Nakagawa, S.1
Saikusa, A.2
Kunttomi, K.3
-
18
-
-
4244088769
-
Courses and limitations of damage with air ingress accidents in HTR modules
-
Paris, France, September 27-29, 1999, Organization for Economic Cooperation and Development
-
W. FRÖHLING, "Courses and Limitations of Damage with Air Ingress Accidents in HTR Modules," Proc. 1st Information Exchange Mtg. Survey on Basic Studies in the Field of High Temperature Engineering, Paris, France, September 27-29, 1999, p. 173, Organization for Economic Cooperation and Development (1999).
-
(1999)
Proc. 1st Information Exchange Mtg. Survey on Basic Studies in the Field of High Temperature Engineering
, pp. 173
-
-
Fröhling, W.1
-
19
-
-
0141461904
-
Aspects of inherent safety of future high temperature reactors
-
Paris, France, September 27-29, 1999, Organization for Economic Cooperation and Development
-
K. KUGELER and P. W. PHLIPPEN, "Aspects of Inherent Safety of Future High Temperature Reactors," Proc. 1st Information Exchange Mtg. Survey on Basic Studies in the Field of High Temperature Engineering, Paris, France, September 27-29, 1999, p. 29, Organization for Economic Cooperation and Development (1999).
-
(1999)
Proc. 1st Information Exchange Mtg. Survey on Basic Studies in the Field of High Temperature Engineering
, pp. 29
-
-
Kugeler, K.1
Phlippen, P.W.2
-
20
-
-
4444310708
-
Safety evaluation during a depressurization accident of the SFHTR
-
Beijing, China, November 2-4, 1998, IAEA-TECDOC-1210, International Atomic Energy Agency
-
S. NAKAGAWA, A. SAIKUSA, and K. KUNITOMI, "Safety Evaluation During a Depressurization Accident of the SFHTR," Proc. Int. Working Group on Gas-Cooled Reactors Mtg., Beijing, China, November 2-4, 1998, IAEA-TECDOC-1210, p. 77, International Atomic Energy Agency (1998).
-
(1998)
Proc. Int. Working Group on Gas-cooled Reactors Mtg.
, pp. 77
-
-
Nakagawa, S.1
Saikusa, A.2
Kunitomi, K.3
-
21
-
-
0030565967
-
Passive heat removal by vessel cooling system of HTTR during no forced cooling accidents
-
K. KUNITOMI, S. NAKAGAWA, and M. SHINOZACHI, "Passive Heat Removal by Vessel Cooling System of HTTR During No Forced Cooling Accidents," Nucl. Eng. Des., 166, 179 (1996).
-
(1996)
Nucl. Eng. Des.
, vol.166
, pp. 179
-
-
Kunitomi, K.1
Nakagawa, S.2
Shinozachi, M.3
-
22
-
-
0141685041
-
Simulation of air ingress with irradiated fuel samples
-
Tokai, Japan, November 9-11, 1994, Japan Atomic Energy Research Institute
-
W. SCHENK, W. FRÖHLING, R. MOORMANN, and H. NABIELEK, "Simulation of Air Ingress with Irradiated Fuel Samples," Proc. 2nd Research Coordination Mtg. Validation of Predictive Methods for Fuel and Fission Product Behavior in Gas-Cooled Reactors, Tokai, Japan, November 9-11, 1994, Japan Atomic Energy Research Institute (1994).
-
(1994)
Proc. 2nd Research Coordination Mtg. Validation of Predictive Methods for Fuel and Fission Product Behavior in Gas-Cooled Reactors
-
-
Schenk, W.1
Fröhling, W.2
Moormann, R.3
Nabielek, H.4
-
23
-
-
33745523551
-
Simulation of nuclide transmutations with Monte-Carlo continuous energy burnup code (MCB 1C)
-
Reno, Nevada, November 11-15, American Nuclear Society (2001) (CD-ROM)
-
J. CETNAR, W. GUDOWSKI, J. WALLENIUS, and K. TUCEK, "Simulation of Nuclide Transmutations with Monte-Carlo Continuous Energy Burnup Code (MCB 1C)," Proc. ANS Topl. Mtg. Accelerator Applications/Accelerator Driven Transmutation Technology Applications (AccApp/ADTTA '01), Reno, Nevada, November 11-15, 2001, American Nuclear Society (2001) (CD-ROM).
-
(2001)
Proc. ANS Topl. Mtg. Accelerator Applications/Accelerator Driven Transmutation Technology Applications (AccApp/ADTTA '01)
-
-
Cetnar, J.1
Gudowski, W.2
Wallenius, J.3
Tucek, K.4
-
24
-
-
13244275692
-
-
EUR 18898 EN, Organization for Economic Cooperation and Development/Nuclear Energy Agency
-
J. CETNAR, W. GUDOWSKI, and J. WALLENIUS, "MCB: A Continuous Energy Monte Carlo Burnup Simulation Code, in Actinide and Fission Product Partitioning and Transmutation," EUR 18898 EN, p. 523, Organization for Economic Cooperation and Development/Nuclear Energy Agency (1999).
-
(1999)
MCB: A Continuous Energy Monte Carlo Burnup Simulation Code, in Actinide and Fission Product Partitioning and Transmutation
, pp. 523
-
-
Cetnar, J.1
Gudowski, W.2
Wallenius, J.3
-
25
-
-
0038172589
-
Investigation of irradiation behavior of siC-coated fuel particle at extended burnup
-
K. SAWA and T. TOBITA, "Investigation of Irradiation Behavior of SiC-Coated Fuel Particle at Extended Burnup," Nucl. Technol., 142, 250 (2003).
-
(2003)
Nucl. Technol.
, vol.142
, pp. 250
-
-
Sawa, K.1
Tobita, T.2
-
26
-
-
33745572466
-
Development of an integrated performance model for TRISO-coated gas reactor particle fuel
-
Petten, The Netherlands, April 22-24, 2002, International Atomic Energy Agency
-
G. K. MILLER, D. A. PETTI, and J. T. MAKI, "Development of an Integrated Performance Model for TRISO-Coated Gas Reactor Particle Fuel," Proc. 1st Int. Topl. Mtg. High Temperature Reactor Technology, Petten, The Netherlands, April 22-24, 2002, International Atomic Energy Agency (2002).
-
(2002)
Proc. 1st Int. Topl. Mtg. High Temperature Reactor Technology
-
-
Miller, G.K.1
Petti, D.A.2
Maki, J.T.3
-
27
-
-
0036706551
-
Long time experience with the development of HTR fuel elements in Germany
-
H. NICKEL et al., "Long Time Experience with the Development of HTR Fuel Elements in Germany," Nucl. Eng. Des., 217, 141 (2002).
-
(2002)
Nucl. Eng. Des.
, vol.217
, pp. 141
-
-
Nickel, H.1
-
28
-
-
33745515894
-
Key differences in the fabrication of U.S. and German TRISO-coated particle fuel, and their implications on fuel performances
-
Petten, The Netherlands, April 22-24, 2002, International Atomic Energy Agency
-
D. A. PETTI, J. BUONGIORNO, J. T. MAKI, and G. K. MILLER, "Key Differences in the Fabrication of U.S. and German TRISO-Coated Particle Fuel, and Their Implications on Fuel Performances," Proc. 1st Int. Topl. Mtg. High Temperature Reactor Technology, Petten, The Netherlands, April 22-24, 2002, International Atomic Energy Agency (2002).
-
(2002)
Proc. 1st Int. Topl. Mtg. High Temperature Reactor Technology
-
-
Petti, D.A.1
Buongiorno, J.2
Maki, J.T.3
Miller, G.K.4
-
29
-
-
33745577445
-
Mathematical model and computer code for coated particles performance at normal operating conditions
-
Petten, The Netherlands, April 22-24, 2002, International Atomic Energy Agency
-
I. GOLUBEV, I. KADARMETOV, and V. MAKAROV, "Mathematical Model and Computer Code for Coated Particles Performance at Normal Operating Conditions," Proc. 1st Int. Topl. Mtg. High Temperature Reactor Technology, Petten, The Netherlands, April 22-24, 2002, International Atomic Energy Agency (2002).
-
(2002)
Proc. 1st Int. Topl. Mtg. High Temperature Reactor Technology
-
-
Golubev, I.1
Kadarmetov, I.2
Makarov, V.3
-
30
-
-
0035079601
-
Coated particle fuel to improve safety, design, and economics in water-cooled and gas-cooled reactors
-
J. PORTA et al., "Coated Particle Fuel to Improve Safety, Design, and Economics in Water-Cooled and Gas-Cooled Reactors," Prog. Nucl. Energy, 38, 407 (2001).
-
(2001)
Prog. Nucl. Energy
, vol.38
, pp. 407
-
-
Porta, J.1
-
31
-
-
0035358402
-
Prediction of fuel performance and fission gas release behavior during normal operation of the high temperature engineering test reactor by JAERI and FZJ modeling approach
-
K. SAWA et al., " Prediction of Fuel Performance and Fission Gas Release Behavior During Normal Operation of the High Temperature Engineering Test Reactor by JAERI and FZJ Modeling Approach," J. Nucl. Sci. Technol., 38, 6, 411 (2001).
-
(2001)
J. Nucl. Sci. Technol.
, vol.38
, Issue.6
, pp. 411
-
-
Sawa, K.1
-
32
-
-
0035438450
-
Safety criteria and quality control of HTTR fuel
-
K. SAWA, S. SUZUKI, and S. SHIOZAWA, "Safety Criteria and Quality Control of HTTR Fuel," Nucl. Eng. Des., 208, 305 (2001).
-
(2001)
Nucl. Eng. Des.
, vol.208
, pp. 305
-
-
Sawa, K.1
Suzuki, S.2
Shiozawa, S.3
-
33
-
-
0035366610
-
Consideration of the effects on fuel particle behavior from shrinkage cracks in the inner pyrocarbon layer
-
G. K. MILLER, D. A. PETTI, D. J. VARACALLE, and J. T. MAKI, "Consideration of the Effects on Fuel Particle Behavior from Shrinkage Cracks in the Inner Pyrocarbon Layer," J. Nucl. Mater., 295, 205 (2001).
-
(2001)
J. Nucl. Mater.
, vol.295
, pp. 205
-
-
Miller, G.K.1
Petti, D.A.2
Varacalle, D.J.3
Maki, J.T.4
-
34
-
-
0035081665
-
Requirements for high temperature reactor fuel particle design assessment
-
P. CHAPELOT et al., "Requirements for High Temperature Reactor Fuel Particle Design Assessment," Prog. Nucl. Energy, 38, 3, 415 (2001).
-
(2001)
Prog. Nucl. Energy
, vol.38
, Issue.3
, pp. 415
-
-
Chapelot, P.1
-
35
-
-
0033688557
-
Fission product release behavior of individual coated fuel particles for high-temperature gas-cooled reactors
-
K. MINATO, K. SAWA, T. KOYA, T. TOMITA, A. ISHIKAWA, C. A. BALDWIN, W. A. GABBARD, and C. M. MALONE, "Fission Product Release Behavior of Individual Coated Fuel Particles for High-Temperature Gas-Cooled Reactors," Nucl. Technol., 131, 36 (2000).
-
(2000)
Nucl. Technol.
, vol.131
, pp. 36
-
-
Minato, K.1
Sawa, K.2
Koya, T.3
Tomita, T.4
Ishikawa, A.5
Baldwin, C.A.6
Gabbard, W.A.7
Malone, C.M.8
-
36
-
-
0029343152
-
Irradiation behavior of HTGR coated particle fuel at abnormally high temperature
-
K. FUKUDA, S. KASHIMURA, T. TOBITA, and T. KIKUCHI, "Irradiation Behavior of HTGR Coated Particle Fuel at Abnormally High Temperature," Nucl. Eng. Des., 157, 221 (1995).
-
(1995)
Nucl. Eng. Des.
, vol.157
, pp. 221
-
-
Fukuda, K.1
Kashimura, S.2
Tobita, T.3
Kikuchi, T.4
-
37
-
-
0027608220
-
Release behavior of metallic fission products from HTGR fuel particles at 1600 and 1900°C
-
K. MINATO et al., "Release Behavior of Metallic Fission Products from HTGR Fuel Particles at 1600 and 1900°C," J. Nucl. Mater., 202, 47 (1993).
-
(1993)
J. Nucl. Mater.
, vol.202
, pp. 47
-
-
Minato, K.1
-
38
-
-
0343738595
-
2 particle fuels subjected to HTR simulated core heating tests
-
Oak Ridge, Tennessee, November 5-8, 1990, IWGGCR-25, International Atomic Energy Agency
-
2 Particle Fuels Subjected to HTR Simulated Core Heating Tests," Proc. Specialists Mtg. Behavior of Gas Cooled Reactor Fuel Under Accident Conditions, Oak Ridge, Tennessee, November 5-8, 1990, IWGGCR-25, p. 132, International Atomic Energy Agency (1990).
-
(1990)
Proc. Specialists Mtg. Behavior of Gas Cooled Reactor Fuel under Accident Conditions
, pp. 132
-
-
Baldwin, C.A.1
Kania, M.J.2
-
39
-
-
0024303932
-
The performance of high-temperature reactor fuel particles at extreme temperatures
-
H. NABIELEK, W. SCHENK, W. HEIT, A. W. MEHNER, and D. T. GOODIN, "The Performance of High-Temperature Reactor Fuel Particles at Extreme Temperatures," Nucl. Technol., 84, 62 (1989).
-
(1989)
Nucl. Technol.
, vol.84
, pp. 62
-
-
Nabielek, H.1
Schenk, W.2
Heit, W.3
Mehner, A.W.4
Goodin, D.T.5
-
40
-
-
0034207748
-
Retention of fission product cesium in ZrC-coated fuel particles for high-temperature gas-cooled reactors
-
K. MINATO et al., "Retention of Fission Product Cesium in ZrC-Coated Fuel Particles for High-Temperature Gas-Cooled Reactors," J. Nucl. Mater., 279, 181 (2000).
-
(2000)
J. Nucl. Mater.
, vol.279
, pp. 181
-
-
Minato, K.1
-
41
-
-
0003183797
-
Irradiation experiment on ZrC-coated fuel particles for high-temperature gas-cooled reactors
-
K. MINATO, T. OGAWA, K. SAWA, A. ISHIKAWA, T. TOMITA, S. IIDA, and H. SEKINO, "Irradiation Experiment on ZrC-Coated Fuel Particles for High-Temperature Gas-Cooled Reactors," Nucl. Technol., 130, 272 (2000).
-
(2000)
Nucl. Technol.
, vol.130
, pp. 272
-
-
Minato, K.1
Ogawa, T.2
Sawa, K.3
Ishikawa, A.4
Tomita, T.5
Iida, S.6
Sekino, H.7
-
42
-
-
0031646220
-
Deterioration of ZrC-coated fuel particle caused by failure of pyrolitic carbon layer
-
K. MINATO et al., "Deterioration of ZrC-Coated Fuel Particle Caused by Failure of Pyrolitic Carbon Layer," J. Nucl. Mater., 252, 13 (1998).
-
(1998)
J. Nucl. Mater.
, vol.252
, pp. 13
-
-
Minato, K.1
-
43
-
-
0031250914
-
Fission product release from Zr-coated fuel particles during post-irradiation heating at 1800 and 2000°C
-
K. MINATO, T. OGAWA, K. FUKUDA, H. SEKINO, I. KITAGAWA, and N. MITA, "Fission Product Release from Zr-Coated Fuel Particles During Post-Irradiation Heating at 1800 and 2000°C," J. Nucl. Mater., 249, 142 (1997).
-
(1997)
J. Nucl. Mater.
, vol.249
, pp. 142
-
-
Minato, K.1
Ogawa, T.2
Fukuda, K.3
Sekino, H.4
Kitagawa, I.5
Mita, N.6
-
45
-
-
4444243210
-
Use of plutonium in pebble bed HTGRs
-
Beijing, China, November 2-4, 1998, IAEA-TECDOC-1210, International Atomic Energy Agency
-
K. KUGELER, W. VON LENSA, G. HAAG, and H. J. RÜTTEN, "Use of Plutonium in Pebble Bed HTGRs," Proc. Int. Working Group on Gas-Cooled Reactors Mtg., Beijing, China, November 2-4, 1998, IAEA-TECDOC-1210, p. 229, International Atomic Energy Agency (1998).
-
(1998)
Proc. Int. Working Group on Gas-cooled Reactors Mtg.
, pp. 229
-
-
Kugeler, K.1
Von Lensa, W.2
Haag, G.3
Rütten, H.J.4
-
46
-
-
0028590670
-
Long term stability of natural glasses
-
Las Vegas, Nevada, May 22-26, 1994, American Nuclear Society
-
V. KNOBLOCH and L. NACHMILNER, "Long Term Stability of Natural Glasses," Proc. 5th Annual Int. Conf. High Level Radioactive Waste Management, Las Vegas, Nevada, May 22-26, 1994, Vol. 2, p. 1066, American Nuclear Society (1994).
-
(1994)
Proc. 5th Annual Int. Conf. High Level Radioactive Waste Management
, vol.2
, pp. 1066
-
-
Knobloch, V.1
Nachmilner, L.2
-
48
-
-
4444374077
-
Generation and benchmarking of a 69 group cross section library for thermal reactor applications
-
J. J. KIM, J. T. LEE, and H. R. KIM, "Generation and Benchmarking of a 69 Group Cross Section Library for Thermal Reactor Applications," J. Korean Nucl. Soc., 21, 245 (1989).
-
(1989)
J. Korean Nucl. Soc.
, vol.21
, pp. 245
-
-
Kim, J.J.1
Lee, J.T.2
Kim, H.R.3
|