Nuclear Systems Volume I: Thermal Hydraulic Fundamentals, Third Edition
by Neil E. Todreas, Mujid S. Kazimi · CRC Press
The reference text for nuclear thermal-hydraulics, used worldwide in graduate courses. Works through single- and two-phase flow, heat transfer, and boiling crisis so you can size coolant channels and check thermal margins in a core.
This link may earn us a small commission at no extra cost to you. Affiliate disclosure
More resources on Nuclear Engineering
Nuclear Reactor Safety (MIT 22.091)
Safety of the complete nuclear power plant: reactor, balance of plant, support systems, their interdependencies and regulatory oversight, taught with plant simulator exercises. Provides six lecture videos, lecture notes, problem sets, exams and assignments, building a systems view of accident prevention.
Nuclear Systems Design Project (MIT 22.033)
Capstone group design project integrating reactor physics, particle transport, heat transfer, control, safety, materials and economics; this offering designs a nuclear power plant tied to carbon sequestration and fossil fuel displacement. Includes 4 lecture videos, instructor insights, and example projects and written assignments.
An MCNP6 Primer
A Kansas State teaching primer, hosted by Los Alamos, for the MCNP radiation transport code. Worked input decks build up geometry, materials, sources, tallies and variance reduction, so you can set up shielding and dose calculations.
OpenMC Documentation
Documentation for the open-source Monte Carlo neutron and photon transport code used across national labs and universities. Pairs a methods guide on transport theory with a Python API and notebooks, so you can run real criticality and depletion calculations.
Perspectives on Reactor Safety (NUREG/CR-6042, Rev. 2)
The NRC Technical Training Center's own course text on nuclear safety concepts. Five modules trace defense in depth, severe accident progression in the vessel, containment behavior, and source terms, giving you the regulator's framework for accident analysis.
Nuclear Reactor Analysis
The standard graduate text on reactor physics, free in full from Michigan's institutional repository. Covers neutron transport, multigroup diffusion, criticality, reactor kinetics and core design, so you can set up and solve core-analysis problems yourself. Repeatedly named the best reactor-physics text; its multigroup diffusion and neutron-transport treatment is the benchmark.