Review of supercritical CO2 power cycle technology and current status of research and development

Supercritical carbon dioxide cycles for power generation: A review

https://scholarsarchive.byu.edu/cgi/viewcontent.cgi?article=2573&context=facpub

Supercritical CO2 Brayton cycles for solar-thermal energy

The development technology and applications of supercritical CO2 power cycle in nuclear energy, solar energy and other energy industries

Generation IV nuclear reactors: current status and future prospects

Preliminary structural evaluations of the STAR-LM reactor vessel and the support design

FASt TEst Reactor (FASTER) design overview

A transient, one dimensional, finite difference computer code (MELTSPREAD-1) has been developed to predict spreading behavior of high temperature melts flowing over concrete and/or steel surfaces submerged in water, or without the effects of water if the surface is initially dry. This paper provides a summary overview of models and correlations currently implemented in the code, code validation activities completed thus far, LWR spreading-related safety issues for which the code has been applied, and the status of documentation for the code.

Status of the MELTSPREAD-1 computer code for the analysis of transient spreading of core debris melts

In the use of large computers to analyze severe accidents in liquid-metal fast breeder reactors (LMFBRs), it has long been recognized that many of the fundamental phenomena cannot be precisely predicted because of uncertainty in the parameters that govern them. As a direct result, mechanistic analysis of such accidents has proceeded along a parametric path in which these variables are fixed at a certain constant value for the entire calculation: The influence of variation of this value is assessed by making a series of complete calculations with the parameter set at a different value for each such element of the series. While some parameters may be thought of as ''correlated'' or fixed for an entire calculation, very few are in fact constant throughout a reactor, and many are (for practical purposes) nearly completely uncorrelated, either in space or time, during the hypothetical accident. Thus, such analysis has created a set of results that are not indicative or representative of an accident involving uncorrelated or only partially correlated variable parameters. A methodology is described for dealing with various degrees of uncertainty or incoherence in these parameters. By using two very different mechanistic codes (FX2-POOL and EPIC), we demonstrate that the treatmentmore » of uncorrelated parameters, such as droplet/particle size in a hypothetical core disruptive accident, as random variables with a certain probability distribution during each complete calculation of a series of calculations produces as much as an order of magnitude less uncertainty in the end result than had been obtained assuming perfect correlation. A small list of parameters is categorized as either correlated or uncorrelated for some of the other LMFBR accident analysis codes. The technique can be easily implemented in a broad spectrum of accident analysis codes with similar benefits.« less

Probabilistic Accident Analysis with Deterministic Codes Using Stochastically Variable Parameters

Supercritical carbon dioxide Brayton cycle power converters can benefit advanced nuclear reactors, as well as small modular reactors, by reducing the plant cost and increasing plant electrical output. The sCO2 cycles can also be designed for operation under direct dry air cooling. The paper presents the results of the coupled control analysis of a sCO2 cycle for a 100 MWe sodium-cooled fast reactor under changing ambient air temperatures. The optimum plant operation modes are identified.

Dynamic Control Analysis of the AFR-100 SMR SFR With a Supercritical CO2 Cycle and Dry Air Cooling: Part II — Plant Control Under Varying Ambient Conditions

James J. Sienicki

Papers

Preliminary structural evaluations of the STAR-LM reactor vessel and the support design

FASt TEst Reactor (FASTER) design overview

Status of the MELTSPREAD-1 computer code for the analysis of transient spreading of core debris melts

Probabilistic Accident Analysis with Deterministic Codes Using Stochastically Variable Parameters

Dynamic Control Analysis of the AFR-100 SMR SFR With a Supercritical CO2 Cycle and Dry Air Cooling: Part II — Plant Control Under Varying Ambient Conditions