Jump to content

User:Markmit/sandbox

From Wikipedia, the free encyclopedia

=Test edits


Taxonomy of nuclear power technologies

[edit]

How are nuclear technologies classed?


Test edits

[edit]

This is a test edit. Code block

``` yadda. ```


History High-temperature reactor development

[edit]

What is a HTR vs a VHTR

Notable development programs and history

Key elements of technology

  • Fuel
  • Pressure vessel
  • power conversion
    • Rankine
    • Gas turbine


First generation and experimental reactors

Second generation

Modular reactors

Nations who have worked on significant programs

Usefuel links

[edit]

Special:Preferences

Articles to link to

[edit]

HANARO

[edit]
Name Location Type Purpose Status Thermal Power [kW] Operation Date Closure Date Owner and Operator Notes
Reactor offical name (Prefer short name). Link to an article if it exists. Nearest city/town. Do not need to add country as the list is grouped by country List of specific types Primary purpose that the reactor was constructed for. Shut down Select from list of status and color the cell, usingTemplate:Table cell templates Thermal power of the reactor in kW. Prefer the first criticality date. Use the table date format YYYY-MM-DD for sorting For status Shutdown -> decomissioned. Prefer the shutdown date not dinal decomissiong date. Use the table date format YYYY-MM-DD for sorting Wikilink to the owner and operator. Additional information on the reactor


System-Integrated Modular Advanced Reactor (SMART)

[edit]


System-Integrated Modular Advanced Reactor (SMART)
Reactor conceptpressurized water reactor, small modular reactor
Main parameters of the reactor core
Fuel (fissile material)U235
Primary moderatorLight Water
Primary coolantLight Water
Reactor usage
Primary useGeneration of Electricity and Desalination.
Power (thermal)330 MW
Power (electric)100 MW
Operator/ownerIn development.
Websitesmart-nuclear.com

SMART (System-integrated Modular Advanced ReacTor) is an integral-type small reactor, developed by KAERI (Korea Atomic Energy Research Institute) after 19 years of research since 1997. It received the first-ever Standard Design Approval (SDA) from Korean regulatory body for a 100 MWe (330 MWt) integral reactor in 2012.

SMART generates only a tenth of a large nuclear plant (over 1,000 MWe), but since it is an integral-type reactor, it has enhanced the inherent safety by containing major components such as pressurizer, steam generator, and reactor coolant pumps in a single reactor pressure vessel. It was designed especially for export and can supply a city with a population of 100,000 with 90 MW electricity and 40,000 tons of fresh water per day concurrently.


History

[edit]

Described below is the brief history of the SMART development.

SMART (System-integrated Modular Advanced ReacTor) is a promising advanced small and medium category nuclear power reactor. It is an integral type reactor with a sensible mixture of proven technologies and advanced design features. SMART aims at achieving enhanced safety and improved economics; the enhancement of safety and reliability is realized by incorporating inherent safety improving features and reliable passive safety systems. The improvement in the economics is achieved through a system simplification, component modularization, reduction of construction time, and high plant availability. The preliminary safety analyses on the selected limiting accidents assure the reliability of the SMART reactor system. Various advanced types of SMRs (small and medium reactors) are currently under development worldwide, and some of them are ready for construction. One beneficial advantage of an SMR is its easy receptivity of advanced design concepts and technology. Drastic safety enhancement can be achieved by adopting inherent safety features and passive safety systems. Economic improvement is pursued through a system simplification, modularization, and reduction of the construction time. SMART, a small-sized integral type PWR with a rated thermal power of 330 MWt, is one of those advanced SMRs. Design characteristics contributing to the safety enhancement are basically inherent safety features such as the integral configuration of the reactor coolant system and an improved natural circulation capability. By introducing a passive residual heat removal system and an advanced LOCA mitigation system, significant safety enhancement is achieved.


Since the Kori nuclear power plant unit 1 - the first nuclear power plant unit ever dedicated in the Rep. of Korea - began commercial operations with a generating capacity of 587 MW in 1978, much research and development has been conducted by the Korean nuclear industry. In the middle 1980s, the Korean Standard Nuclear Power Plant (KSNP) was first developed under the "Nuclear Power Promotion Plan" promulgated by the government with reference to the System 80 of ABB-CE of the USA. Applying indigenously accumulated technologies and up-to-date design standards from both home and abroad, the initial KSNP project began with the construction of the Younggwang NPP units No. 3 and 4. In addition, the Korea Atomic Energy Research Institute (KAERI) designed and constructed a high-performance, multipurpose research reactor based on experience in the operation of previous reactors and accumulated nuclear technology. Timed with completion of construction in April 1995, the reactor was named HANARO (high-flux advanced neutron application reactor), which in Korean means, "uniqueness". Since 1997, KAERI has been developing the system-integrated modular advanced reactor (SMART), an advanced integral pressurized water reactor (PWR), that can be used for seawater desalination or district heat generation as well as electricity generation. Described below is the brief history of the major SMART development milestones.

  • 2012 Acquired standard design approval for SMART reactorAcquired standard design approval for SMART, which places primary components in a single leak-tight pressure vessel. Succeeded in obtaining first-ever standard design approval for an integrated reactor.


Conceptual Design Development of the SMART-330 (’97.07 ~ ’99.03)

[edit]

Concept of an integral reactor SMART with a rated thermal power of 330 MWt was developed in this early period. SMART-330 aims to generate 90 MWe of electricity and produce 40,000 m3/day of desalinated water. Preliminary design bases, functional requirements and safety requirements were established. Conceptual development was carried out for the reactor core, primary fluid system, and structural components. Basic thermo-hydraulic tests were performed including heat transfer characteristics with nitrogen gas and natural convection performance test. Feasibility studies were also performed through a mockup fabrication of the steam generator cassette, control rod drive mechanism and reactor coolant pump.

Basic Design for the SMART-330 (’99.04 ~ ’02.03)

[edit]

The basic design of the integral reactor SMART with a rated thermal power of 330 MWt was completed in March of 2002. A model of reactor vessel assembly was completed and design methodologies including computer codes were set up. Preliminary safety analyses were performed to show the overall integrity of the reactor system. The concept of an integrated nuclear desalination plant coupled with SMART has been established. Design for an optimal coupling of the multi-effect distillation (MED) system with SMART focused on the economic use of energy and system safety. Preliminary analysis estimates that the amount of water and electricity produced are sufficient for a population of about 100,000.

Development of the SMART-Pilot Plant (’02.07 ~ ’06.02)

[edit]

After reviewing and evaluating the 330 MWt SMART on safety, economics, and reliability, a detail design and construction project for a pilot plant at 1/5 scale (65 MWt) of the SMART, called SMART-P, was launched in July of 2002. The purpose of the SMART-P project was to demonstrate the SMART technologies and assess the overall performance and safety. T he first phase focused on the design optimization and technology verification by way of tests and experiments such as high-temperature and high-pressure hydraulic tests, pressurizer heat transfer tests, and corrosion evaluation tests. At the completion of the first phase, detailed design including the fuel and BOP was established and the construction permit of the SMART-P was submitted to the Korean nuclear regulatory authority.

Pre-Project Service for the SMART Reactor System Development (’06.07 ~ ’07.06)

[edit]

A pre-project service for the SMART reactor system development was carried out to conclude the scheme of the design optimization and to ascertain the economical feasibility prior to the commencement of the national R&D commercialization program. For this purpose, the results of the basic design development for SMART and the pending technical items derived during the licensing process of SMART-P were evaluated and the engineering solutions were pursued. Optimized design concept of the SMART reactor system was developed, and the fabricability and maintenance scheme of the major facilities and equipments were scrutinized and supplemented to enhance their technical completeness, licensability and economical efficiency. Thermal power of SMART was up-rated to 660 MWt to further improve its economical efficiency, and its design concepts were modified from several aspects to better adjust to the licensing requirements.

SMART Technology Verification and Standard Design Approval Program (’09.01 ~ ’12.12)

[edit]

A comprehensive technology verification process including twenty or more separate effect tests and performance tests will be performed under the program. Standard design for SMART will be developed jointly with the participating industries, and a full spectrum of licensing documents will be prepared for a licensing review by the Korean license authority (KINS). This certified design material will comply with the Korean rules and regulations currently applied to the large scale PWRs in operation and under construction in the Rep. of Korea. The applied codes and standards will be equivalent to those of the internationally acknowledged ones.

Design

[edit]

The SMART core is designed to produce a thermal energy of 330MW with 57 fuel assemblies of a 17x17 array. The SMART core design providing an inherent safety is characterized by: Longer cycle operation with a two-batch reload scheme Low core power density Adequate thermal margin of more than 15 % Inherently free from xenon oscillation instability Minimum rod motion for the load follows with coolant temperature control SMART fuel management is designed to achieve a maximum cycle length between a refuelling. A simple two-batch refuelling scheme without reprocessing returns a cycle of 990 effective full power days (EFPD) for a 36 month operation. This reload scheme minimizes complicated reload design efforts, and thus enhances fuel utilization. The SMART fuel management scheme is highly flexible to meet customer requirements.

External interest

[edit]

SMART Partnership with KSA MOU signed between MISP and K.A.CARE An MOU was signed between the Ministry of Science, ICT and Future Planning (MSIP) of South Korea and the King Abdullah City for Atomic and Renewable Energy (K.A.CARE) of the Kingdom of Saudi Arabia on March 3, 2015. It was signed in Riyadh, Saudi Arabia following a summit meeting between both countries. Under the agreement, both countries will conduct three-year pre-project engineering to prepare preliminary safety analysis report of FOAK plants in Saudi Arabia. The MOU also calls for both countries to cooperate on the commercialization and promotion of the SMART reactor to third countries.

  • Joint Execution of Pre-Project Engineering (PPE)
  • Establishment of SMART Power Company (SPC)
  • Construction of 2 Units of SMART by SPC in Saudi Arabia
  • Human Capacity Building for Saudi Experts
  • Joint Marketing of SMART to 3rd Countries


See also

[edit]
[edit]

References

[edit]