Fast Reactors and Accelerator Driven Systems Knowledge Base

Country Index to IAEA TECDOCs by Author Affiliation

USA

Status of (UPu)C and (UPu)N fuel development in BARC
Ganguly, C.; Hegde, P.V.; Sengupta, A.K. (Bhabha Atomic Research Centre, Bombay (India). Radiometallurgy Div.)
IAEA-TECDOC--466, pp:8-24

Neutron irradiation effects in fusion or spallation structural materials: Some recent insights related to neutron spectra
Garner, F.A.;Greenwood, L.R. (Pacific Northwest National Lab., Richland, WA (United States))
IAEA-TECDOC--1039, pp:15-36

United States national program on Actinide Recycle. Summary
Khalil, H. (Argonne National Lab., IL (United States))
IAEA-TECDOC--693, pp:21-22

Summary: “A roadmap for developing accelerator transmutation of waste (ATW) technology”. A report to Congress
J.C. Bresee (Office of Civilian Radioactive Waste Management, Department of Energy, United States of America)
IAEA-TECDOC--1365, pp:59-63

Actinide transmutation in the advanced liquid metal reactor (ALMR)
Cockey, C.L. (General Electric Co., San Jose, CA (United States). Nuclear Energy Div.)
IAEA-TECDOC--693, pp:61-66

The Gulf General Atomic gas-cooled fast breeder reactor system
Fortescue, P
IAEA-TECDOC--154, pp:62-77

Status of liquid metal reactor development in the United States of America
Chernock, W.; Horton, K.E. (Department of Energy, Washington, DC (United States). Office of Nuclear Energy)
IAEA-TECDOC--791, pp:68-87

Physics considerations in the design of liquid metal reactors for transuranium element consumption
Khalil, H.; Hill, R.; Fujita, E.; Wade, D. (Argonne National Lab., IL (United States))
IAEA-TECDOC--693, pp:70-73

A competitive thorium fuel cycle for pressurized water reactors of current technology
Galperin, A.; Radkowsky, A. (Ben-Gurion University of the Negev, Beer-Sheva (Israel)); Todosow, M. (Brookhaven National Laboratory, Upton, NY (United States))
IAEA-TECDOC--1319, pp:83-96

Neutronics design studies of an LBE cooled ATW blanket
W.S. Yang, H.S. Khalil
IAEA-TECDOC--1356, pp:83-93

Status of liquid metal reactor development in the United States of America
Griffith, J.F.; Horton, K.E. (Department of Energy, Washington, DC (United States). Office of Nuclear Energy)
IAEA-TECDOC--741, pp:85-103

Physics studies for sodium cooled ATW blanket
R.N. Hill, H.S. Khalil
IAEA-TECDOC--1356, pp:94-109

Nuclear energy research initiative: Thorium fuel cycle projects
Thompson, C.A. (Office of Nuclear Energy, Science and Technology, United States Department of Energy, Germantown, MD (United States))
IAEA-TECDOC--1319, pp:97-103

Two-tiered approach for light water reactor waste disposition using existing light water reactors and a minor actinide burner
H.R. Trellue, E.J. Pitcher, P. Chodak III, D. Bennett
IAEA-TECDOC--1356, pp:110-119

New concepts for small power reactors without on-site refuelling for non-proliferation
Brown, N.W.; Hasberger, J.A. (Lawrence Livermore National Laboratory, Livermore, CA (United States))
IAEA-TECDOC--1172, pp:117-128

Core physics performance of recycled LWR discharge TRU oxide fuel in a GT/AD-MHR
T.A. Taiwo, Y. Gohar, P.J. Finck
IAEA-TECDOC--1356, pp:120-133

The economics of transmutation fuel cycles
D. Kim, M.S. Kazimi, M.J. Driscoll, N.E. Todreas
IAEA-TECDOC--1356, pp:134-147

Decommissioning experience from the experimental breeder reactor-II
Henslee, S.P.; Rosenberg, K.E. (Argonne National Laboratory-West (ANL-W), Idaho Falls (United States))
IAEA-TECDOC--1405, pp:137-140

Current US plans for development of fuels for accelerator transmutation of waste
D.C. Crawford, S.L. Hayes, M.K. Meyer
IAEA-TECDOC--1356, pp:151-163

Chemical separations technologies for the US accelarator transmutation of waste programme
J.J. Laidler
IAEA-TECDOC--1356, pp:164-167

Impact of fuel choices on spent fuel characteristics for once-through heavy metal cooled reactors
P.Heyzlar, M.J. Driscoll, N.E. Todreas
IAEA-TECDOC--1356, pp:168-185

Development of martensitic steels for high neutron damage applications
Gelles, D.S. (Battelle Pacific Northwest National Lab., Richland, WA (United States))
IAEA-TECDOC--1039, pp:169-178

Experimental testing of reduced scale seismic isolation bearings for the advanced liquid metal reactor
Aiken, D.; Clark, P.W.; Kelly, J.M. (Earthquake Engineering Research Center, University of California at Berkeley, Berkeley, CA (United States))
IAEA-TECDOC--1288, pp:191-249

Los Alamos ATT programme
Francesco Venneri, LANL, USA
IAEA-TC--903.3, pp:195-203

Variability of irradiation creep and swelling of HT9 irradiated to high neutron fluence at 400-600 deg.C
Toloczko, M.B.;Garner, F.A. (Pacific Northwest National Lab., Richland, WA (United States))
IAEA-TECDOC--1039, pp:197-209

Control of accelerator driven subcritical systems fuelled by actinides
Rief, H. (Commission of the European Communities, Ispra (Italy). Ispra Establishment); Takahashi, H. (Brookhaven National Lab., Upton, NY (United States))
IAEA-TECDOC--783, pp:209-217

Liquid metal fast reactor transient design
Horak, C.; Purvis, E. III (Energy and Nuclear Technology Division, Brookhaven National Laboratory, Upton, New York (United States))
IAEA-TECDOC--1180, pp:226-237

A re-evaluation of helium/dpa and Hydrogen/dpa ratios for fast reactor and thermal reactor data used in fission-fusion correlations
Garner, F.A.;Greenwood, L.R. (Pacific Northwest National Lab., Richland, WA (United States))
IAEA-TECDOC--1039, pp:239-249

An accelerator-driven reactor for meeting future energy demand
Hiroshi Takahashi, U.Yang, and An Yu Brookhaven National Laboratory
IAEA-TC--903.3, pp:239-244

Design criteria and mitigation options for thermal fatigue effects in ATW blankets
F.E. Dunn
IAEA-TECDOC--1356, pp:240-250

Thorium-based fuel design for incineration of excess weapon grade plutonium in existing PWRs
Galperin, A. (Ben-Gurion University of the Negev (Israel)); Todosow, M. (Brookhaven National Laboratory, Upton, NY (United States))
IAEA-TECDOC--1319, pp:251-256

Preliminary safety analysis of a Swedish accelerator driven system employing nitride fuel and burnable absorbers
M. Eriksson, J. Wallenius, K. Tucek, W. Gudowski, J. Cahalan
IAEA-TECDOC--1356, pp:251-264

Corrosion of structural materials by lead based reactor coolants
D.P. Abraham, L. Leibowitz, V.A. Maroni, S.M. McDeavitt, A.G. Raraz
IAEA-TECDOC--1356, pp:329-339

A kinetic model for corrosion and precipitation in non-isothermal LBE flow loop
X. He, N. Li, M. Mineev
IAEA-TECDOC--1356, pp:340-351

Requirements of a proton beam accelerator for an accelerator-driven reactor
H.Takahashi, Y Zhao. N.Tsuopas, Y. An, and Y. Yamazaki
IAEA-TC--903.3, pp:375-380