Feasibility of a Nuclear Reactor Dedicated to Desalination

2014 ◽  
Author(s):  
Yong Hun Jung ◽  
Yong Hoon Jeong ◽  
Jang Sik Moon
Keyword(s):  
Nuclear Reactor ◽  
Significant Loss ◽  
Safety Issues ◽  
Nuclear Heat ◽  
Thermal Desalination ◽  
Economic Analyses ◽  
Safety Features ◽  
Low Pressures ◽  
Current Energy ◽  
Target Country

The development of a small-sized nuclear heat-only plant with maximized safety features dedicated to seawater thermal desalination was proposed to address both a serious water crisis and nuclear safety issues, which continue to be perennial problems. In this study, the feasibility of a dedicated nuclear heat-only desalination system for a target country was evaluated in comparison with a target nuclear thermal desalination system. First, the target country was selected, and its current energy and desalination status was investigated. The suitable nuclear desalination options for the target country were then selected. Finally, using corresponding analysis tools, performance and economic analyses were conducted for a dedicated nuclear heat-only desalination system and the target nuclear thermal desalination system. The results of the analyses indicate that operating the small-sized nuclear heat-only plant at low pressures coupled with a seawater thermal desalination plant will considerably improve both the safety and economy without a significant loss in desalination performance. In conclusion, the proposed dedicated nuclear heat-only desalination system is expected to have high potential for solving both problems.

Status of District Heating Reactor and its Development Prospects in China

2018 ◽  
Author(s):  
Jing Zhao ◽  
Fei Xie ◽  
Zhihong Liu
Keyword(s):  
Low Temperature ◽  
Nuclear Reactor ◽  
District Heating ◽  
Heating System ◽  
Inherent Safety ◽  
Nuclear Heating Reactor ◽  
New Type ◽  
Nuclear Heating ◽  
Safety Features ◽  
Temperature Heating

Nuclear heating reactor is a new type of power plant that uses nuclear energy as heat source. Low temperature nuclear heating reactor should be the forerunner and main force for developing nuclear heating plant in China. Due to the lower water temperature required by the heating system, this dedicated, non-power generating nuclear reactor works at low temperatures and pressures with inherent safety features. The design, construction and operation of the nuclear heating reactors in various countries in the world were reviewed in this paper, and China’s new demonstration nuclear heating project and NHR-200 low-temperature heating reactor which would be used was discussed in the paper. We put forward the developing route and suggestion for the development of low-temperature heating reactor in China.

scholarly journals THE CORRELATION OF THE CATEGORIES OF “QUALITY” AND “SAFETY” OF PRODUCTS

2019 ◽  
pp. 74-78
Author(s):  
T.V. Malanchuk ◽  
E.A. Zaitsev
Keyword(s):  
Civil Rights ◽  
Legal Regulation ◽  
Poor Quality ◽  
Product Safety ◽  
Legal Rights ◽  
Safety Issues ◽  
State Supervision ◽  
Safety Features ◽  
And Control

The article analyzes the complex state of the modern legislative regulation of quality and product safety issues in the context of ensuring consumers’ rights to the proper quality of goods (works, services). It is stated that in view of the variety of different properties that make up the notion of quality, the most important are the defects, which are capable of damaging the life, health, or property of the consumer, that is, the defects, which indicate that the goods are dangerous. The safety of goods works, and services as a legal category are of particular importance and is one of the functions of the state to ensure public safety. State measures of influence on manufacturers and sellers of goods, persons who perform work and provide services should be aimed at ensuring the protection of fundamental civil rights. In most cases, these are imperative requirements for safety, which are approved by special legal acts, as well as measures of state supervision and control to ensure the safety of manufactured goods, works, and services. The legislator, when defining security, uses the term “safety of goods (works, services)”, but it would be advisable to carry out graduation of these concepts since the safety of goods is a state of goods that allows it to be sold, used, stored, transported, disposed of without harm for life, health, the property of the consumer and the environment in normal conditions, and the safety of works and services is the quality of protection of the legal rights of the consumer in carrying out the activities of persons who perform work and provide services, danger to life, health, the property should not manifest itself either in their implementation and providing or later. It is noted that quality requirements should be made mandatory when designing production specifications. It is stated that in order to ensure the effectiveness of legal regulation, the safety of a product, work, or service must be considered as a full-fledged property within the legal notion of quality. It is concluded that product safety is an integral feature of any product, work, and service, acting as an integral element of the quality category. Lack of safety features indicates that the product is of poor quality. Keywords: quality, safety, proper quality, improper quality, specifications, consumers.

The fast-neutron breeder fission reactor: safety issues in reactor design and operation

1990 ◽  
Vol 331 (1619) ◽  
pp. 409-418 ◽  
Keyword(s):  
Reactor Core ◽  
Liquid Sodium ◽  
Metallic Fuel ◽  
Safety Issues ◽  
Fission Reactor ◽  
Core Energy ◽  
Proper Design ◽  
Breeder Reactors ◽  
Uranium Plutonium ◽  
Safety Features

Today’s fast breeder reactors contain mixed uranium —plutonium oxide fuel and are cooled with liquid sodium. Their normal operational behaviour, including power transients, is similar to that of thermal reactors. The fact that the sodium density coefficient is positive is of no importance at normal operating temperatures because negative coefficients like Doppler or fuel expansion coefficients have compensating effects. Dangerous effects may arise when sodium boiling at much higher temperatures occur. It is shown that sodium boiling in most cases can be avoided by proper design of the reactor core. Energy releases associated with partial destruction of the core are discussed. The safety features of metallic fuel are briefly discussed, resulting in the statement that in principle, use of metallic fuel does not promise more positive safety features.

Effect of Neutron Irradiation on the Mechanical Properties of an A508 CL2 and 15Kh2NMFA Irradiated in the NOMAD_3 Rig in the BR2 Cooling Water

2021 ◽  
Author(s):  
Inge Uytdenhouwen ◽  
Rachid Chaouadi
Keyword(s):  
Neutron Irradiation ◽  
Nuclear Reactor ◽  
Cooling Water ◽  
Charpy Impact ◽  
Tensile Tests ◽  
Significant Loss ◽  
Irradiation Temperature ◽  
Irradiation Damage ◽  
Transition Curves ◽  
Reactor Pressure

Abstract The typical operating temperatures of a nuclear reactor pressure vessel in a PWR are between 290°C and 300°C. However, many BWRs and some PWRs operate at slightly lower temperatures down to 260°C. Most of the literature and neutron irradiation damage is therefore focused on those irradiation temperatures. It is well-known that the lower the irradiation temperature, the more neutron irradiation damage occurs, because no appreciable annealing happens below approximately 230°C. The NOMAD_3 irradiation consisted in total of 24 Charpy sized samples from an A508 Cl.2 forging and a 15Kh2NMFA material. They were irradiated to three various fluences between 1.55 and 7.90 × 1019 n/cm2 (E > 1MeV) at approximately 100°C. The hardening of the A508 Cl.2 was between 260 and 400 MPa which was much higher than the NOMAD_0 properties which were irradiated at approximately 280°C. The tensile tests of irradiated materials are all characterized by a significant loss of work hardening capacity leading to plastic flow localization promptly after the yield strength is reached. This affects also the shape of the Charpy impact transition curves. The radiation embrittlement derived from Charpy impact tests, ΔT41J, is up to 156°C for the highest fluence. For this irradiation, the embrittlement to hardening ratio was also around 0.43 +/−0.2°C/MPa as it was found in the previous campaign NOMAD_0. This paper discusses the tensile, hardness and impact properties of the NOMAD_3 irradiation campaign. It is compared to the NOMAD_0 with respect to effect of irradiation temperature and annealing recovery.

Enhancing Probabilistic Risk Assessment Methodology for Solving Reactor Safety Issues

2003 ◽  
Author(s):  
F. L. Cho
Keyword(s):  
Nuclear Reactor ◽  
Severe Accident ◽  
Assessment Methodology ◽  
Reactor Safety ◽  
Reactor Accident ◽  
Safety Issues ◽  
Damage States ◽  
Baseline Information ◽  
Risk Assessment Methodology ◽  
Accident Sequences

This paper reveals a paradigm of analyzing the consequential effects of severe nuclear reactor accident, radionuclides fraction and source terms release, that will influence the MACCS2 codification [1], by coupling with the results of SAPHIA-PSA Levels l & 2 quantification process [2], MELCORE [3], STCP [4], PST [5], and XSOR [6]. Those codes are mutually exclusive and useful. However, it lacks of the closed interface and linkage for addressing Plant Damage States (PDS), Severe Accident Sequences, and Risk Consequence. Thus, it is imperative to formulate the consistent baseline information for MACCS2, PSA Levels 1, 2 and 3, and then linking to a new algorithm of NCM.

INPRO Assessment of an INS in the Area of Safety of Fuel Cycle Installations

2006 ◽  
Author(s):  
B. Raj ◽  
Y. Busurin ◽  
F. Depisch
Keyword(s):  
Nuclear Reactor ◽  
Fuel Cycle ◽  
Early Stage ◽  
Sol Gel ◽  
Safety Issues ◽  
Stage Of Development ◽  
Energy Needs ◽  
Fuel Fabrication ◽  
Specific Assessment ◽  
Acceptance Limits

INPRO has defined requirements organized in a hierarchy of Basic Principles, User Requirements and Criteria (consisting of an indicator and an acceptance limit) to be met by innovative nuclear reactor systems (INS) in six areas, namely: economics, safety, waste management, environment, proliferation resistance, and infrastructure. If an INS meets all requirements in all areas it represents a sustainable system for the supply of energy, capable of making a significant contribution to meeting the energy needs of the 21st century. Draft manuals have been developed, for each INPRO area, to provide guidance for performing an assessment of whether an INS meets the INPRO requirements in a given area. The manuals set out the information that needs to be assembled to perform an assessment and provide guidance on selecting the acceptance limits and, for a given INS, for determining the value of the indicators for comparison with the associated acceptance limits. Each manual also includes an example of a specific assessment to illustrate the guidance. This paper discusses the manual for performing an INPRO assessment in the area of safety of fuel cycle installations. The example, chosen solely for the purpose of illustrating the INPRO methodology, describes an assessment of an MOX fuel fabrication plant based on sol-gel technology and illustrates an assessment performed for an INS at an early stage of development. The safety issues and the assessment steps are presented in detail in the paper.

A New Safety Principle For The Slowpoke Reactor

2013 ◽  
Vol 2 (1) ◽  
pp. 113-118 ◽  
Author(s):  
S. Yue ◽  
S. Polugari ◽  
V. Anghel ◽  
J. Hilborn ◽  
B. Sur
Keyword(s):  
Nuclear Reactor ◽  
Thermal Power ◽  
Reactor Operation ◽  
Simulink Model ◽  
Negative Reactivity ◽  
Full Power ◽  
Safety Features ◽  
Pool Type ◽  
High Neutron ◽  
High Neutron Flux

SLOWPOKE-2 (LEU core) is a pool-type nuclear reactor with a maximum nominal thermal power of 20 kW. It uses a pelletized uranium oxide fuel (19.9% enrichment) and provides a useful high neutron flux in the order of 1012 n.cm2s-1. The key safety features built into the reactor design are the strictly limited amount of excess reactivity and the negative reactivity feedback characteristics, which provide a demonstrably safe self-limiting power excursion response to large reactivity insertions. However, the limited amount of excess reactivity also limits continuous prolonged reactor operation at full power. With a 4 mk excess reactivity, the reactor can operate for about one day at full power, 20 kW, before criticality is lost due to temperature effects and xenon poisoning. A new safety concept is proposed in this paper that enables the continuous operation to a few months by increasing the excess reactivity from 4 mk to 8 mk. A Matlab/simulink model of SLOWPOKE-2 has demonstrated that core operation life can be extended to several months without adding a beryllium shim.

Thermal-Hydraulic Model and Program Development for Helium-Cooled Accelerator-Driven System

2017 ◽  
Vol 3 (2) ◽  
Author(s):  
Tianji Peng ◽  
Zhiwei Zhou
Keyword(s):  
Nuclear Reactor ◽  
Cooling System ◽  
Three Dimensional ◽  
Coupling Model ◽  
Hydraulic Model ◽  
Minor Actinide ◽  
Conduction Model ◽  
Transient Model ◽  
Waste Products ◽  
Safety Features

The accelerator-driven subcritical reactor system (ADS) is a kind of nuclear reactor which can burn minor actinide waste products produced from conventional reactors with inherent safety features. In this paper, the thermal-hydraulic model and a corresponding program for a 10 MW helium-cooled experimental ADS are presented. Through the analysis of the heat transfer mechanism in ADS, the thermal-hydraulic model of ADS was built, in which the solid domain is simulated with three-dimensional heat conduction model and the fluid domain is simulated with the one-dimensional quasi-static model. In order to analyze the transient characteristics of ADS with cooling system, a RELAP5–TRCAP coupling model for the cooling system was established, in which the decay heat of the target and core is considered. The results of steady condition and transients demonstrate the effectiveness of the transient model.

scholarly journals Former Food Products Safety Evaluation: Computer Vision as an Innovative Approach for the Packaging Remnants Detection

2017 ◽  
Vol 2017 ◽  
pp. 1-6 ◽  
Author(s):  
Marco Tretola ◽  
Matteo Ottoboni ◽  
Ambra Rita Di Rosa ◽  
Carlotta Giromini ◽  
Eleonora Fusi ◽  
...  
Keyword(s):  
Computer Vision ◽  
Safety Evaluation ◽  
Food Products ◽  
Alternative Source ◽  
Basic Principles ◽  
Safety Issues ◽  
Advantages And Disadvantages ◽  
Animal Feeding ◽  
Food Losses ◽  
Safety Features

Former food products (FFPs) represent a way by which leftovers from the food industry (e.g., biscuits, bread, breakfast cereals, chocolate bars, pasta, savoury snacks, and sweets) are converted into ingredients for the feed industry, thereby keeping food losses in the food chain. FFPs represent an alternative source of nutrients for animal feeding. However, beyond their nutritional value, the use of FFPs in animal feeding implies also safety issues, such as those related to the presence of packaging remnants. These contaminants might reside in FFP during food processing (e.g., collection, unpacking, mixing, grinding, and drying). Nowadays, artificial senses are widely used for the detection of foreign material in food and all of them involve computer vision. Computer vision technique provides detailed pixel-based characterizations of colours spectrum of food products, suitable for quality evaluation. The application of computer vision for a rapid qualitative screening of FFP’s safety features, in particular for the detection of packaging remnants, has been recently tested. This paper presents the basic principles, the advantages, and disadvantages of the computer vision method with an evaluation of its potential in the detection of packaging remnants in FFP.

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