Author: John R. Huffman
Publisher:
ISBN:
Category : Materials testing reactors
Languages : en
Pages : 28
Book Description
The Materials Testing Reactor as an Irradiation Facility
Author: John R. Huffman
Publisher:
ISBN:
Category : Materials testing reactors
Languages : en
Pages : 28
Book Description
Publisher:
ISBN:
Category : Materials testing reactors
Languages : en
Pages : 28
Book Description
Irradiation Facilities at the Advanced Test Reactor
Author: S. Blaine Grover
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
The Advanced Test Reactor (ATR) is the third generation and largest test reactor built in the Reactor Technology Complex (RTC - formerly known as the Test Reactor Area), located at the Idaho NationalLaboratory (INL), to study the effects of intense neutron and gamma radiation on reactor materials and fuels. The RTC was established in the early 1950s with the development of the Materials Testing Reactor (MTR), which operated until 1970. The second major reactor was the Engineering Test Reactor (ETR), whichoperated from 1957 to 1981, and finally the ATR, which began operation in 1967 and will continue operation well into the future. These reactors have produced a significant portion of the world's data on materials response to reactor environments. The wide range of experiment facilities in the ATR and the unique ability to vary the neutron flux in different areas of the core allow numerous experiment conditions to co-exist during the same reactor operating cycle. Simple experiments may involve a non-instrumented capsule containingtest specimens with no real-time monitoring or control capabilities1. More sophisticated testing facilities include inert gas temperature control systems and pressurized water loops that have continuous chemistry, pressure, temperature, and flow control as well as numerous test specimen monitoring capabilities. There are also apparatus that allow for the simulation of reactor transients on test specimens.
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
The Advanced Test Reactor (ATR) is the third generation and largest test reactor built in the Reactor Technology Complex (RTC - formerly known as the Test Reactor Area), located at the Idaho NationalLaboratory (INL), to study the effects of intense neutron and gamma radiation on reactor materials and fuels. The RTC was established in the early 1950s with the development of the Materials Testing Reactor (MTR), which operated until 1970. The second major reactor was the Engineering Test Reactor (ETR), whichoperated from 1957 to 1981, and finally the ATR, which began operation in 1967 and will continue operation well into the future. These reactors have produced a significant portion of the world's data on materials response to reactor environments. The wide range of experiment facilities in the ATR and the unique ability to vary the neutron flux in different areas of the core allow numerous experiment conditions to co-exist during the same reactor operating cycle. Simple experiments may involve a non-instrumented capsule containingtest specimens with no real-time monitoring or control capabilities1. More sophisticated testing facilities include inert gas temperature control systems and pressurized water loops that have continuous chemistry, pressure, temperature, and flow control as well as numerous test specimen monitoring capabilities. There are also apparatus that allow for the simulation of reactor transients on test specimens.
Handbook of Materials Testing Reactors and Associated Hot Laboratories in the European Community
Author: Peter von der Hardt
Publisher: Springer
ISBN:
Category : Science
Languages : en
Pages : 168
Book Description
Publisher: Springer
ISBN:
Category : Science
Languages : en
Pages : 168
Book Description
Irradiation Services at the Materials Testing Reactor
Author: National Reactor Testing Station, Idaho (U.S.)
Publisher:
ISBN:
Category : Irradiation
Languages : en
Pages : 22
Book Description
Publisher:
ISBN:
Category : Irradiation
Languages : en
Pages : 22
Book Description
Gamma Facilities at the Materials Testing Reactor
Author: Brewer F. Boardman
Publisher:
ISBN:
Category : Gamma rays
Languages : en
Pages : 10
Book Description
Publisher:
ISBN:
Category : Gamma rays
Languages : en
Pages : 10
Book Description
The Advanced Test Reactor Irradiation Facilities and Capabilities
Author: Raymond V. Furstenau
Publisher:
ISBN:
Category : Irradiation
Languages : en
Pages : 16
Book Description
"The Advanced test Reactor (ATR) is the third generation of test reactors built at the Test Reactor Area (TRA), located in the Idaho National Engineering and Environmental Laboratory (INEEL), to study the effects of intense neutron and gamma radiation on reactor materials and fuels. ART has a maximum power of 250MW and can provide maximum thermal neutron fluxes of 1E15 neutrons per square centimeter per second. this allows considerable acceleration of accumulated neutron fluence to materials and fuels over what would be seen in a typical power reactor. Since power operation of the ATR began in 1969, numerous testing methods have been developed to take advantage of the capabilities of the ATR. The wide range of experimental facilities in the ATR and the unique ability to vary the neutron flux in different areas of the core allow numerous experiment conditions to co-exist during the same reactor operating cycle. Simple experiments may involve a non-instrumented sealed capsule containing test specimens with no real-time monitoring and control capabilities. More sophisticated testing facilities include inert gas temperature control systems and pressurized water loops that have continuous chemistry, pressure, temperature, and flow control as well as numerous test specimen monitoring capabilities. There are also apparatus that allow for the simulation of reactor transients on test specimens. The Irradiation Test Vehicle, installed in 1999, is the newest testing apparatus in the ATR that accommodates up to fifteen separate tests, each with its own temperature control and monitoring capabilities as well as neutron spectral tailoring capability. The U.S. Department of Energy intends to maintain and expand the capabilities of the ATR to ensure it remains a viable facility for the Department's materials and fuels testing programs for the foreseeable future." -- Page[1].
Publisher:
ISBN:
Category : Irradiation
Languages : en
Pages : 16
Book Description
"The Advanced test Reactor (ATR) is the third generation of test reactors built at the Test Reactor Area (TRA), located in the Idaho National Engineering and Environmental Laboratory (INEEL), to study the effects of intense neutron and gamma radiation on reactor materials and fuels. ART has a maximum power of 250MW and can provide maximum thermal neutron fluxes of 1E15 neutrons per square centimeter per second. this allows considerable acceleration of accumulated neutron fluence to materials and fuels over what would be seen in a typical power reactor. Since power operation of the ATR began in 1969, numerous testing methods have been developed to take advantage of the capabilities of the ATR. The wide range of experimental facilities in the ATR and the unique ability to vary the neutron flux in different areas of the core allow numerous experiment conditions to co-exist during the same reactor operating cycle. Simple experiments may involve a non-instrumented sealed capsule containing test specimens with no real-time monitoring and control capabilities. More sophisticated testing facilities include inert gas temperature control systems and pressurized water loops that have continuous chemistry, pressure, temperature, and flow control as well as numerous test specimen monitoring capabilities. There are also apparatus that allow for the simulation of reactor transients on test specimens. The Irradiation Test Vehicle, installed in 1999, is the newest testing apparatus in the ATR that accommodates up to fifteen separate tests, each with its own temperature control and monitoring capabilities as well as neutron spectral tailoring capability. The U.S. Department of Energy intends to maintain and expand the capabilities of the ATR to ensure it remains a viable facility for the Department's materials and fuels testing programs for the foreseeable future." -- Page[1].
High Flux Materials Testing Reactor HFR Petten
High Flux Materials Testing Reactor, HFR Petten : characteristics of facilities and standard irradiation devices
High Flux Materials Testing Reactor HFR Petten
Irradiation Technology
Author: Peter von der Hardt
Publisher: Springer Science & Business Media
ISBN: 940097115X
Category : Technology & Engineering
Languages : en
Pages : 733
Book Description
The International Topical Meeting on Irradiation Technology took place two the Neutron and its Applications (Cambridge, weeks after the Conference on th U. K.) marking the 50 anniversary of the discovery of the neutron. The application of neutrons from research reactors for materials testing requires a large variety of irradiation devices (vehicles) and their out-of-pile control and recording equipment. The in-pile sections are sophisticated in design and assem bly, expensive, and consumable. There have been only a few international con ferences on irradiation testing, the last one being limited to fast breeder reactor work (Jackson, Wyoming, September 1973). In 1982, however, two conferences picked up similar topics -the ANS Conference on Fast, Thermal, and Fusion Reactor Experiments (Salt Lake City, Utah, April 1982), -the Grenoble meeting (these proceedings). Overlapping has been avoided by putting the accent of the U.S. conference on fast reactor work, and on thermal reactor experiments at Grenoble. Put to gether, both conferences ligned up more than 130 papers in this very specialised field, demonstrating a high level of technological development as opposed to a decreasing number of large materials testing reactors available. The editors wish to acknowledge the flawless organisation of the meeting by CEN de Grenoble and the personal commitment of CEN staff to its success. Special thanks go to F. Merchie andJ.F. Veyrat of the Service des Piles. P. von der Hardt H. R6ttger XIII P. von der Hardt and H. Rottger (eds.), Irradiation Technology, xiii.
Publisher: Springer Science & Business Media
ISBN: 940097115X
Category : Technology & Engineering
Languages : en
Pages : 733
Book Description
The International Topical Meeting on Irradiation Technology took place two the Neutron and its Applications (Cambridge, weeks after the Conference on th U. K.) marking the 50 anniversary of the discovery of the neutron. The application of neutrons from research reactors for materials testing requires a large variety of irradiation devices (vehicles) and their out-of-pile control and recording equipment. The in-pile sections are sophisticated in design and assem bly, expensive, and consumable. There have been only a few international con ferences on irradiation testing, the last one being limited to fast breeder reactor work (Jackson, Wyoming, September 1973). In 1982, however, two conferences picked up similar topics -the ANS Conference on Fast, Thermal, and Fusion Reactor Experiments (Salt Lake City, Utah, April 1982), -the Grenoble meeting (these proceedings). Overlapping has been avoided by putting the accent of the U.S. conference on fast reactor work, and on thermal reactor experiments at Grenoble. Put to gether, both conferences ligned up more than 130 papers in this very specialised field, demonstrating a high level of technological development as opposed to a decreasing number of large materials testing reactors available. The editors wish to acknowledge the flawless organisation of the meeting by CEN de Grenoble and the personal commitment of CEN staff to its success. Special thanks go to F. Merchie andJ.F. Veyrat of the Service des Piles. P. von der Hardt H. R6ttger XIII P. von der Hardt and H. Rottger (eds.), Irradiation Technology, xiii.