Using the MCNP and ONEDANT analysis codes, we investigated basic neutronic characteristics of the NP-MHTGR preconceptual design. Exploratory steady-state analyses of k{sub eff}, neutron reaction rates, andtemperature reactivity coefficients were conducted to check die ability of our reactor physics methods to adequately model the highly heterogeneous NP-MHTGR reactor. Results of unit-fuel-cell analyses indicate that a three-region ONEDANT model adequately approximates the unit-fuel-cell lattice geometry. However, core-block analyses indicate that approximating an hexagonal heterogeneous block by a one-dimensional annular target cell can introduce significant calculational error. Investigating the core-block temperature coefficient of reactivity, we found that all components of the coefficient are negative and the delayed component contributes {approx}85% of the total temperature effect. Investigation of the full reactor temperature coefficient in the NP-MHTGR determined that all contributions from the active core are negative, with prompt effects again contributing {approx}15% of the total core coefficient Temperature-coefficient contributions from each of the reflector regions appear to be positive, but exhibit a smaller magnitude than those in the core. These positive contributions apparently are caused by reduced carbon and boron absorptions at the higher reflector temperatures. From a safety perspective, a conclusion as to the adequacy of the temperature coefficient cannot be drawn from its magnitude alone, but must be based on specific transient or accident analyses which incorporate all feedback effects. Calculational differences between MCNP and ONEDANT were as high as {approx} 1.2% for the reactor criticality eigenvalue and on the order of 20% for the core temperature coefficient
