Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1997. / Includes bibliographical references. / by Yin-Ching Iris Chen. / Ph.D.

Thesis (M.S.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1997. / Includes bibliographical references (leaf 102). / by Imad Maurice Jureidini. / M.S.

Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1998. / Includes bibliographical references (leaves 117-124). / by Jec-Kong Gone. / Ph.D.

Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1998. / Includes bibliographical references (p. 80-82). / The Versatile Toroidal Facility (VTF) at MIT's Plasma Science and Fusion Center provides a laboratory environment for studying ionospheric plasmas. Various plasma diagnostic devices have been created and used to study the VTF plasma since 1991. An accurate method for measuring VTF's ion characteristics has never been designed or installed in the laboratory facility. Gridded Energy Analyzers (GEA) are useful diagnostic tools for determining plasma ion energy distributions and ion temperature. Research was done on the theory behind Gridded Energy Analyzers and their applicability for use in the Versatile Toroidal Facility. A design and method for constructing a miniaturized GEA for VTF was developed and documented. The construction method covers material selection, machining, and assembly of VTF's miniature GEA. The miniature GEA is a non-perturbing probe used in VTF's plasma, which is approximately 3 cm in diameter. The GEA was constructed and preliminary experimental data was obtained. From this data VTF's ion temperature was found to be approximately 8eV and an ion distribution function was determined to be roughly Maxwellian in nature. / by Shaun L. Meredith. / S.M.

Thesis (M.S.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1992. / Includes bibliographical references (leaves 136-138). / by Sandra Lee Harms. / M.S.

Massachusetts Institute of Technology. Dept. of Nuclear Engineering. Thesis. 1973. Sc.D. / Leaves 38 and 87 used twice. / Bibliography: leaves 250-251. / Sc.D.

Thesis (S.B.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 2001. / Includes bibliographical references (leaves 64-65). / This thesis sets the groundwork for a numerical benchmark of the VSOP code suite, which has the potential of being an integral part of the design and licensing of future modular high temperature gas reactor designs. The goal of this thesis was to develop models, techniques, and data to be used in a future verification of the VSOP code. Pebble bed critical experiments carried out on the Swiss PROTEUS facility were chosen as a starting point for a pebble bed benchmark using the Monteburns code. Monteburns, a linking code that uses the ORIGEN2 code to burn MCNP inputs, was used to evaluate the neutronics of the PROTEUS LEUPRO-1 unit cell. Models were made at various levels of simplification for the actual spherical geometry as well as the equivalent cylindrical geometry, to test their ability to reproduce results described in several published reports. These models were then used to calculate reactivity, spectral indices, and bumup isotopics for a cold 100 MWD/kgU burnup scenario. The results of these calculations showed that the methods employed in this thesis are in good agreement with work previously published regarding benchmarking of codes on LEUPRO-1: k-inf differences are generally less than 0.5%. The Monteburns burnup isotopics were compared to results from a CASMO-4 burn of the cylindrical geometry equivalent of the LEUPRO-1 unit cell with excellent agreement, even better than that typically achieved for LWR unit cell benchmarks. The results provide a reliable basis for proceeding with the benchmarking of the VSOP code's burnup capabilities at MIT and elsewhere. / by Jeremy Robert Johnson. / S.B.

Thesis (Sc. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1996. / Includes bibliographical references. / by Hui Zhu. / Sc.D.

Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1990. / Includes bibliographical references (leaves 217-221). / by Rene G. Sanchez. / Ph.D.

Thesis (S.M. and S.B.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 2005. / Includes bibliographical references (p. 75-76). / The use of multiple frequencies of electron cyclotron resonance heating (ECRH) in the Levitated Dipole Experiment (LDX) is an important tool that will tailor the plasma profiles. Initial LDX plasmas have been created using 2.45 GHz and 6.4 GHz, both at up to 3 kW. The construction and calibration of the ECRH system will be discussed and initial experimental results will be presented. The effects of different combinations of pulse lengths and powers will be examined in terms of the plasma diamagnetism. Different density profiles will be used to calculate the locations of the resonances and cutoffs. Locations where the plasma absorbs the microwave power will be simulated through computer codes. Equilibrium output of the program DIPOLEQ combined with MATLAB calculations using the Appleton-Hartree dispersion relation provide qualitative representations of where the power is absorbed in typical LDX plasmas. / by Scott B. Mahar. / S.M.and S.B.