DEPLESYN : a three dimensional, discontinuous synthesis, diffusion-depletion code. by Chin, Ronald Joseph.

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Optimization of the axial power shape in pressurized water reactors by Melik, M. A

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MITR-II fuel management, core depletion, and analysis : codes developed for the diffusion theory program CITATION by Bernard, John Albert

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Improved multidimensional numerical methods for the steady state and transient thermal-hydraulic analysis of fuel pin bundles and nuclear reactor cores. by Masterson, Robert Edward.

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Application of nodal equivalence theory to the neutronic analysis of PWRS by Hoxie, Christopher Lloyd

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Approximate methods for obtaining a one-group nodal solution with two-group parameters by Hagemeier, Bruce William

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Development of a method for BWR subchannel analysis. by Faya, Artur José Goncalves

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Comparison of conservative and best estimate heat transfer packages with COBRA-IV-I. by Massoud, Mahmoud

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Improved multidimensional numerical methods for the steady state and transient thermal-hydraulic analysis of fuel pin bundles and nuclear reactor cores by Masterson, Robert Edward, Wolf Lothar

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Sensitivity study of the assembly averaged thermal-hydraulic models of the MEKIN computer code in power transients by Rodack, Thomas

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Investigation of solution techniques for large sparse band width matrix equations of linear systems by Guillebaud, Louis Jean Marie, Golay M.

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An improved long range fuel management program by Beard, Charles Louis

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An Introduction to the THERMIT thermal hydraulic reactor computer codes at M.I.T. by Parsons, Donald Kent, Todreas, Neil E., Kazimi, Mujid S., Lanning, David D.

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Availability of the THERMIT thermal hydraulic reactor computer codes through M.I.T. by Parsons, Donald Kent, Todreas, Neil E., Kazimi, Mujid S., Lanning, David D.

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Sensitivity study of the assembly averaged thermal-hydraulic models of the MEKIN computer code in power transients / by Thomas Rodack [and] Lothar Wolf by Rodack, Thomas, Wolf, Lothar

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Optimization of the axial power shape in pressurized water reactors by Malik, Mushtaq Ahmad, Kamal, Altamash, Driscoll, Michael J., Lanning, David D.

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The fuel cycle economics of improved uranium utilization in light water reactors by Abbaspour Tehrani Fard, Ali, Driscoll Michael J.

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Reactor thermal-hydraulic analysis improvement and application of the code COBRA-IIIC/MIT by Loomis, James North

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