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1DB, a one-dimensional diffusion code for nuclear reactor analysis (WHC ; WHC-EP-0435)

1DB, a one-dimensional diffusion code for nuclear reactor analysis (WHC ; WHC-EP-0435)
Paper図書
W.W. Little, Jr.1991
Other Libraries in Japan

Reactivity changes during startup of large nuclear rockets

Reactivity changes during startup of large nuclear rockets
Microform博士論文
Little, W. W., Jr.Massachusetts Institute of Technology1964.<F-DI-4045m>
National Diet Library

Fuel cycle analysis of a thorium fueled spectral shift reactor

Fuel cycle analysis of a thorium fueled spectral shift reactor
Microform博士論文
Little, W. W. Jr.Massachusetts Institute of Technology1962.<F-DI-1299m-MIT62-545>
National Diet Library
  • Author HeadingLittle, W. W. Jr.

User's manual for the 1DX-2DB-3DB-PERT-V code package (BNWL ; BNWL-1412)

User's manual for the 1DX-2DB-3DB-PERT-V code package (BNWL ; BNWL-1412)
Paper図書
Hardie, R.W., Little, W.W. Jr.Battelle-Northwest, Pacific Northwest Lab.1970.7.
Other Libraries in Japan

3DB: A three-dimensional diffusion theory burnup code (BNWL ; BNWL-1264)

3DB: A three-dimensional diffusion theory burnup code (BNWL ; BNWL-1264)
Paper図書
Hardie, R.W., Little, W.W. Jr.Battelle-Northwest, Pacific Northwest Lab.1970.3.
Other Libraries in Japan

1DX: A one-dimensional diffusion code for generating effective nuclear cross sections (BNWL ; BNWL-954)

1DX: A one-dimensional diffusion code for generating effective nuclear cross sections (BNWL ; BNWL-954)
Paper図書
Hardie, R.W., Little, W.W. Jr.Battelle-Northwest, Pacific Northwest Lab.1969.3.
Other Libraries in Japan

2DB user's manual. Revision 1 (BNWL ; BNWL-831(Rev.1))

2DB user's manual. Revision 1 (BNWL ; BNWL-831(Rev.1))
Paper図書
Little, W.W. Jr., Hardie, R.W.Battelle-Northwest, Pacific Northwest Lab.1969.8.
Other Libraries in Japan

PERT-V: A two-dimensional perturbation code for fast reactor analysis (BNWL ; BNWL-1162)

PERT-V: A two-dimensional perturbation code for fast reactor analysis (BNWL ; BNWL-1162)
Paper図書
Hardie, R.W., Little, W.W. Jr.Battelle-Northwest, Pacific Northwest Lab.1969.9.
Other Libraries in Japan

Nuclear parameters and parametric studies for the fast test reactor (FTR) (BNWL ; BNWL-1067)

Nuclear parameters and parametric studies for the fast test reactor (FTR) (BNWL ; BNWL-1067)
Paper図書
Little, W.W. Jr., Maas, L.L.Battelle-Northwest, Pacific Northwest Lab.1969.6.
Other Libraries in Japan

2DB user's manual (BNWL ; BNWL-831)

2DB user's manual (BNWL ; BNWL-831)
Paper図書
Little, W.W. Jr., Hardie, R.W.Battelle-Northwest, Pacific Northwest Lab.1968.7.
Other Libraries in Japan

A numerical comparison of diffusion and transport (S/sub n/) codes for selected fast reactor configurations (BNWL ; BNWL-992)

A numerical comparison of diffusion and transport (S/sub n/) codes for selected fast reactor configurations (BNWL ; BNWL-992)
Paper図書
O'Dell, L.D., Hardie, R.W., Little, W.W. Jr.Battelle-Northwest, Pacific Northwest Lab.1969.3.
Other Libraries in Japan

2DB: A two dimensional diffusion-burnup code for fast reactor analysis (BNWL ; BNWL-640)

2DB: A two dimensional diffusion-burnup code for fast reactor analysis (BNWL ; BNWL-640)
Paper図書
Little, W.W. Jr., Hardie, R.W.Battelle-Northwest, Pacific Northwest Lab.1968.1.
Other Libraries in Japan

FCC-IV: A revised version of the FCC fundamental mode fast reactor code (BNWL ; BNWL-450)

FCC-IV: A revised version of the FCC fundamental mode fast reactor code (BNWL ; BNWL-450)
Paper図書
Little, W.W.Jr., Hardie, R.W.Battelle-Northwest, Pacific Northwest Lab.1967.8.
Other Libraries in Japan

MAX: A one-dimensional maximum hypothetical accident code in FORTRAN-IV (BNWL ; BNWL-612)

MAX: A one-dimensional maximum hypothetical accident code in FORTRAN-IV (BNWL ; BNWL-612)
Paper図書
Little, W.W. Jr.Battelle-Northwest, Pacific Northwest Lab.1968.3.
Other Libraries in Japan

PERT-IV: A two-dimensional perturbation code in fortran-IV (BNWL ; BNWL-409)

PERT-IV: A two-dimensional perturbation code in fortran-IV (BNWL ; BNWL-409)
Paper図書
Hardie, R.W., Little, W.W. Jr.Battelle-Northwest, Pacific Northwest Lab.1967.4.
Other Libraries in Japan

Multigroup analysis of selected fast critical assemblies (BNWL ; BNWL-347)

Multigroup analysis of selected fast critical assemblies (BNWL ; BNWL-347)
Paper図書
Little, W.W. Jr., Hardie, R.W., Maas, L.L.Battelle-Northwest, Pacific Northwest Lab.1966.12.
Other Libraries in Japan

Neutronics characteristics of selected compact fast reactors (BNWL ; BNWL-283)

Neutronics characteristics of selected compact fast reactors (BNWL ; BNWL-283)
Paper図書
Little, W.W. Jr., Hardie, R.W.Battelle-Northwest, Pacific Northwest Lab.1966.7.
Other Libraries in Japan

K-III: A three region kinetics code in Fortran-IV (BNWL ; BNWL-252)

K-III: A three region kinetics code in Fortran-IV (BNWL ; BNWL-252)
Paper図書
Little, W.W. Jr.Battelle-Northwest, Pacific Northwest Lab.1966.6.
Other Libraries in Japan

NEUTRONICS CHARACTERISTICS OF SELECTED COMPACT FAST REACTORS (BNWL ; BNWL-283)

NEUTRONICS CHARACTERISTICS OF SELECTED COMPACT FAST REACTORS (BNWL ; BNWL-283)
Paper図書
Little, W.W. Jr./Hardie, R.W.Battelle Pacific Northwest Laboratories(Battelle Pacific Northwest Laboratories)1966.
Other Libraries in Japan

Neutronics characteristics of four possible driver fuels for the Fast Test Reactor (FTR) (BNWL ; BNWL-281)

Neutronics characteristics of four possible driver fuels for the Fast Test Reactor (FTR) (BNWL ; BNWL-281)
Paper図書
Little, W.W. Jr., Hardie, R.W.Battelle-Northwest, Pacific Northwest Lab.1966.5.
Other Libraries in Japan
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