Neutronic and Thermodynamic System Solution of the Nuclear Power Plant

This work proposes a paradigm shift in nuclear safety. Its NCV Method (neutronics/calorimetrics/verification procedures) integrates nuclear power’s motive force—neutron flux—within Second Law exergy analysis, coupled with corrected conservation of energy flows, both descriptive of the entire system. These descriptions with two satellite equations result in a verifiable understanding of the nuclear engine: neutron flux [or neutronic terms f (Φ)], useful power produced, and system heat rejection, all coupled to reactor vessel coolant mass flow. Key to NCV is its assumption that all nuclear phenomena are inertial processes, devoid of terrestrial reference. This approach demands reinterpretation of Einstein’s ΔE = c²Δm by describing his ΔE as an exergetic potential, an ultimate Free Exergy. For fission, Free Exergy consists of both recoverable and irreversible portions given a total MeV release. In transference to the coolant, the recoverable release produces an exergetic increase (Δg) in the fluid; an explicitly calculated Inertial Conversion Factor produces a computed Core Thermal Power (Δh) and a nuclear T_Ref.

This paper asserts that traditional nuclear engineering has lacked direct linkage between neutron flux and system fluid thermodynamics. With NCV, nuclear power’s motive force is explicitly related to extensive properties, thus allowing reconciliation of principal system parameters of the nuclear engine (fission source, power out, heat rejection, and main system flow). Principal verification is accomplished by comparing the computed useful power to that which is directly measured. The NCV method has the potential to reduce uncertainty in computed Core Thermal Power from its commonly accepted ±2% by an order of magnitude. Its ability to improve plant safety becomes intrinsic, for example:

 ● tracking changes in verifiable flux versus reactor vessel coolant flow;