A preliminary systems-engineering study of an advanced nuclear-electrolytic hydrogen-production facility

An advanced nuclear-electrolytic hydrogen-production facility concept was synthesized at a conceptual level with the objective of minimizing estimated hydrogen-production costs. The concept is a closely-integrated, fully-dedicated (only hydrogen energy is produced) system whose components and subsystems are predicted on ''1985 technology.'' The principal components are: (1) a high-temperature gas-cooled reactor (HTGR) operating a helium-Brayton/ammonia-Rankine binary cycle with a helium reactor-core exit temperature of 980 C, (2) acyclic d-c generators, (3) high-pressure, high-current-density electrolyzers based on solid-polymer electrolyte technology. Based on an assumed 3,000 MWt HTGR the facility is capable of producing 8.7 million std cu m/day of hydrogen at pipeline conditions, 6,900 kPa. Coproduct oxygen is also available at pipeline conditions at one-half this volume. It has further been shown that the incorporation of advanced technology provides an overall efficiency of about 43 percent, as compared with 25 percent for a contemporary nuclear-electric plant powering close-coupled contemporary industrial electrolyzers

Studies of the use of high-temperature nuclear heat from an HTGR for hydrogen production

The results of a study which surveyed various methods of hydrogen production using nuclear and fossil energy are presented. A description of these methods is provided, and efficiencies are calculated for each case. The process designs of systems that utilize the heat from a general atomic high temperature gas cooled reactor with a steam methane reformer and feed the reformer with substitute natural gas manufactured from coal, using reforming temperatures, are presented. The capital costs for these systems and the resultant hydrogen production price for these cases are discussed along with a research and development program

Energy Conversion Alternatives Study (ECAS), General Electric Phase 1. Volume 3: Energy conversion subsystems and components. Part 1: Bottoming cycles and materials of construction

Energy conversion subsystems and components were evaluated in terms of advanced energy conversion systems. Results of the bottoming cycles and materials of construction studies are presented and discussed

Applications of aerospace technology in the electric power industry

An overview of the electric power industry, selected NASA contributions to progress in the industry, linkages affecting the transfer and diffusion of technology, and, finally, a perspective on technology transfer issues are presented

Closed Brayton Cycle power system with a high temperature pellet bed reactor heat source for NEP applications

Capitalizing on past and future development of high temperature gas reactor (HTGR) technology, a low mass 15 MWe closed gas turbine cycle power system using a pellet bed reactor heating helium working fluid is proposed for Nuclear Electric Propulsion (NEP) applications. Although the design of this directly coupled system architecture, comprising the reactor/power system/space radiator subsystems, is presented in conceptual form, sufficient detail is included to permit an assessment of overall system performance and mass. Furthermore, an attempt is made to show how tailoring of the main subsystem design characteristics can be utilized to achieve synergistic system level advantages that can lead to improved reliability and enhanced system life while reducing the number of parasitic load driven peripheral subsystems

ANALYSIS OF COGENERATION ENERGY CONVERSION SYSTEM DESIGN IN IPWR REACTOR

The acceleration of national development, especially in the industrial sector, requires an adequate national energy supply. There are various types of energy sources which include conventional energy sources as well as new and renewable energy sources including nuclear energy. The problem is how to utilize these energy sources into energy that is ready to be utilized. BATAN as a research and development institution in the nuclear field has taken the initiative to contribute to the development of technology for providing electricity and other thermal energy, particularly reactor technology as a power plant and a provider of thermal energy. This research aims to analyze the design of the IPWR type SMR reactor cogeneration energy conversion system. The IPWR reactor cogeneration energy conversion system which also functions as a reactor coolant is arranged in an indirect cycle configuration or Rankine cycle. Between the primary cooling system and the secondary cooling system is mediated by a heat exchanger which also functions as a steam generator. The analysis was carried out using ChemCAD computer software to study the temperature characteristics and performance parameters of the IPWR reactor cogeneration energy conversion system. The simulation results show that the temperature of saturated steam coming out of the steam generating unit is around 505.17 K. Saturated steam is obtained in the reactor power range between 40 MWth to 100 MWth. The results of the calculation of the energy utilization factor (EUF) show that the IPWR cogeneration configuration can increase the value of the energy utilization factor up to 91.20%

Analysis of a 115MW, 3 shaft, helium Brayton cycle

This research theme is originated from a development project that is going on in South Africa, for the design and construction of a closed cycle gas turbine plant using gas-cooled reactor as the heat source to generate 115 MW of electricity. South African Power utility company, Eskom, promotes this developmental work through its subsidiary called PBMR (Pebble Bed Modular Reactor). Some of the attractive features of this plant are the inherent and passive safety features, modular geometry, small evacuation area, small infrastructure requirements for the installation and running of the plant, small construction time, quick starting and stopping and also low operational cost. This exercise is looking at the operational aspects of a closed cycle gas turbine, the finding of which will have a direct input towards the successful development and commissioning of the plant. A thorough understanding of the fluid dynamics in this three-shaft system and its transient performance analysis were the two main objectives of this research work. A computer programme called GTSI, developed by a previous Cranfield University research student, has been used in this as a base programme for the performance analysis. Some modifications were done on this programme to improve its control abilities. The areas covered in the performance analysis are Start-up, Shutdown and Load ramping. A detailed literature survey has been conducted to learn from the helium Turbo machinery experiences, though it is very limited. A critical analysis on the design philosophy of the PBMR is also carried out as part of this research work. The performance analysis has shown the advantage, disadvantage and impact of various power modulation methods suggested for the PBMR. It has tracked the effect of the operations of the various valves included in the PBMR design. The start-up using a hot gas injection has been analysed in detail and a successful start region has been mapped. A start-up procedure is also written based on this. The analysis on the normal and emergency load rejection using various power modulation devices has been done and it stress the importance of more control facilities during full load rejection due to generator faults. A computational fluid dynamics (CFD) analysis, using commercial software, has been carried out on some geometry of the PBMR design to find out whether its flow characteristic will have any serious impact on the performance on the cycle during the load control of the plant. The analysis has demonstrated that there will not be much impact on the performance, during load control using pressure level changes, from this geometry. However, some locations in the geometry have been identified as areas where the flow is experiencing comparatively high pressure losses. Recommendations, which include modification in the physical design, were made to improve this. The CFD analysis has extended to a cascade to compare the flow behaviour of Air and Helium with an objective of using air, being inexpensive, to test the helium flow characteristic in a test rig to simulate the behavioural pattern of helium in the PBMR pressure vessel. The specification of a hypothetical test rig and the necessary scaling parameters has been derived from this exercise. This will be useful for designing test rigs during the developmental and operational stage of the PBMR project

COMPARATIVE ANALYSIS OF COOLANT MASS FLOW RATE FOR PELUIT-40 REACTOR IN ENERGY CONVERSION SYSTEM: A STUDY OF CONCEPTUAL DESIGN WITH AND WITHOUT A SPLITTER

PeLUIt-40 is a nuclear reactor being designed in Indonesia for heat utilizing and generating electricity, with a thermal power of 40 MW. To improve energy efficiency, a system of electricity power and heat generation for hydrogen production called a cogeneration system was developed. The purpose of this study is to determine the best design for the cogeneration system. In this study, two conceptual designs of the cogeneration system were simulated, i.e., with and without a splitter system, respectively. The effect of coolant mass flow rate from (5, 6, 7, 8, 9, 10, 11, 12, 13, and 14 kg/s) to the energy utilization factor were analyzed. Calculations were performed using the ChemCAD 6.4.1 program and Python programming. The result shows that an increase of the coolant mass flow rate will increase the exit temperature of the coolant secondary side as a result of the heat transfer in the Intermediate Heat Exchanger (IHX). This temperature impacts an increase in the thermal power used for power generation and heat production. An increase in the mass flow rate in both designs also causes the value of the energy utilization factor (Energy Utilization Factor-EUF) and the value of the thermal efficiency to increase. Using the splitter has an EUF value of 34.51%, while the without splitter design is 33.92%. Likewise, the efficiency value of both with a splitter and without a splitter are 71.02% and 69.92%

Possibilities of nuclear powered agro-industrial complexes for iran

Nuclear powered industrial and agro-industrial complexes are new concepts that can make major contributions to industrial, agriculatural and general economic advancement in Jran. The production of wer,. water and steam from a Iarge nuclear power plant can provide cheap supplies for numerous industties such as petrochemical industries (including oil refineries), chemical fertilizers, caustic soda and chlorine production as well as the aluminium and steel industries. The state-of-art in the field is reviewed atid" the"possibilities of creating agro-industrial complexes in lran are discussed. The conditions of lran are reviewed. Energy and water requirements are explained. The most economical methods of water desalination are. reviewed. Conditions under which desalted water may be used for agriculture are explained. The type of nuclear power plants ordered for Jran are presented. Some of the environmental effects are discussed. Previous studies on the subject are also mentioned. Problems of implementation of such a program are briefty presented. A feasibility study of the subject for lran is recommended