Measurement of neutron spectrum in an AGN-201 reactor using a semiconductor neutron spectrometer.

Neutronic Analysis For Nuclear Reactor Systems /
by: Zohuri, Bahman
Published: (2019)

Neutron emission measurements from actinide waste isotopes /
by: Saleh, Habeeb H., 1964-
Published: (1995)

The measeurement of the neutron spectrum of a fast critical assembly using proton recoil proportional counting.
by: Lozito, Edward Joseph
Published: (1974)

Neutron cross sections for fast reactor materials /
by: Schmidt, J. J. (Josef Johannes), 1931-
Published: (1966)

An analysis of the time interval distribution of neutron pulses from a nuclear reactor.
by: Williams, Ronald John
Published: (1969)

Design and simulation of a boron-loaded neutron spectrometer.
by: Martin, Thomas
Published: (2012)

The theory of neutron slowing down in nuclear reactors
by: Ferziger, Joel H.
Published: (1966)

Neutron thermalization in reactor lattice cells ; an NPY-Project report /
by: Stamm'ler, R. J. J.
Published: (1966)

The measurement of absolute thermal neutron flux using liquid scintillation counting techniques.
by: Walker, Jack Vernon
Published: (1960)

Delayed neutrons from the neutron irradiation of ²³⁵U /
by: Heinrich, Aaron David, 1980-
Published: (2008)

An experimental study of spatial effects on mean neutron lifetime measurement.
by: Hooke, William Bruce
Published: (1966)

An introduction to the neutron kinetics of nuclear power reactors /
by: Tyror, J. G.
Published: (1970)

An introduction to the neutron kinetics of nuclear power reactors /
by: Tyror, J. G., et al.
Published: (1970)

Lithium fluoride thermoluminescent responses to neutrons.
by: Weng Pao-Shan
Published: (1966)

Neutron computed tomography /
by: Russell, Clifford Marlow, 1968-

Reduced enrichment neutronics evaluation for Texas A&M Nuclear Science Center Reactor /
by: Parthasarathy, Rajalakshmi, 1964-
Published: (1989)

Delayed neutron measurements from fast fission of actinide waste isotopes /
by: Charlton, William S., 1973-
Published: (1997)

The spatial behavior of neutron flux during power reactor transients as effected by the xenon-iodine chain.
by: Sumpter, James Robert
Published: (1970)

The development and demonstration of a thermal neutron radiography facility utilizing the TAMU NSC TRIGA reactor.
by: Lorenz, Robert Wayne
Published: (1972)

Scattered neutron tomography based on a neutron transport problem /
by: Scipolo, Vittorio, 1980-
Published: (2005)

Neutron Imaging : Basics, Techniques and Applications /
Published: (2022)

Monte Carlo determination of the neutron-gamma spectrum behind cadmium loaded polyethylene slabs irradiated by the Sandia Pulse Reactor III /
by: Sartor, Raymond Francis
Published: (1986)

Three dimensional neutronics calculations for the TAMU Nuclear Science Center Triga reactor using BOLD VENTURE /
by: Yupari, Ricardo, 1961-
Published: (1985)

Nuclear data guide for reactor neutron metrology /
Published: (1989)

General Electric PETtrace cyclotron as a neutron source for boron neutron capture therapy /
by: Bosko, Andrey, 1977-
Published: (2005)

Neutron activation analysis applied to perspiration electrolytes.
by: McAndrew, Robert Gavin
Published: (1969)

Axial propagation of neutron waves in heterogeneous media.
by: Quddus, Mohammad Abdul, 1936-
Published: (1968)

Neutron detection.
by: Allen, William Douglas, 1914-
Published: (1960)

Evaluation and application of delayed neutron precursor data /
by: Brady, Michaele Clarice, 1959-
Published: (1988)

Development of a portable neutron coincidence counter for field measurements of nuclear materials using the advanced multiplicity capabilities of MCNPX 2.5.F and the neutron coincidence point model /
by: Thornton, Angela Lynn, 1982-
Published: (2008)

The nuclear fuel of pressurized water reactors and fast neutron reactors : design and behaviour /
Published: (1999)

Neutron monitoring /
Published: (1967)

The Neutron's children : nuclear engineers and the shaping of identity /
by: Johnston, Sean, 1956-
Published: (2012)

[AGN reactor manual].
Published: (1956)

Neutronics evaluation of the replacement fuel for the Texas A&M Nuclear Science Center TRIGA Reactor /
by: Shelton, Gary Ross, 1963-
Published: (1989)

Research reactor application for materials under high neutron fluence.
Published: (2011)