Fuel Melting and Relocation in the Advanced Test Reactor

Fuel Melting and Relocation in the Advanced Test Reactor PDF Author: Jeffrey Scott Gundersen
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ISBN:
Category :
Languages : en
Pages : 172

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Fuel Melting and Relocation in the Advanced Test Reactor

Fuel Melting and Relocation in the Advanced Test Reactor PDF Author: Jeffrey Scott Gundersen
Publisher:
ISBN:
Category :
Languages : en
Pages : 172

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Fuel Melting and Relocation in the Advanced Test Reactor

Fuel Melting and Relocation in the Advanced Test Reactor PDF Author: Mark Handrick
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ISBN:
Category :
Languages : en
Pages : 184

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Analysis of the Reactor Physics of Low-Enrichment Fuel for the INL Advanced Test Reactor in Support of RERTR.

Analysis of the Reactor Physics of Low-Enrichment Fuel for the INL Advanced Test Reactor in Support of RERTR. PDF Author:
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ISBN:
Category :
Languages : en
Pages :

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Analysis of the performance of the ATR with a LEU fuel design shows promise in terms of a core design that will yield the same neutron sources in target locations. A proposed integral cladding burnable absorber design appears to meet power profile requirements that will satisfy power distributions for safety limits. Performance of this fuel design is ongoing; the current work is the initial evaluation of the core performance of this fuel design with increasing burnup. Results show that LEU fuel may have a longer lifetime that HEU fuel however, such limits may be set by mechanical performance of the fuel rather that available reactivity. Changes seen in the radial fuel power distribution with burnup in LEU fuel will require further study to ascertain the impact on neutron fluxes in target locations. Source terms for discharged fuel have also been studied. By its very nature, LEU fuel produces much more plutonium than is present in HEU fuel at discharge. However, the effect of the plutonium inventory appears to have little affect on radiotoxicity or decay heat in the fuel.

Fuel/target Relocation Experiments

Fuel/target Relocation Experiments PDF Author:
Publisher:
ISBN:
Category : Materials testing reactor
Languages : en
Pages : 168

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Irradiation of the First Advanced Gas Reactor Fuel Development and Qualification Experiment in the Advanced Test Reactor

Irradiation of the First Advanced Gas Reactor Fuel Development and Qualification Experiment in the Advanced Test Reactor PDF Author:
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ISBN:
Category :
Languages : en
Pages :

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The United States Department of Energy's Advanced Gas Reactor (AGR) Fuel Development and Qualification Program will be irradiating eight separate tri-isotopic (TRISO) particle fuel (in compact form) experiments in the Advanced Test Reactor (ATR) located at the Idaho National Laboratory (INL). These irradiations and fuel development are being accomplished to support development of the next generation reactors in the United States. The ATR has a long history of irradiation testing in support of reactor development and the INL has been designated as the United States Department of Energy's lead laboratory for nuclear energy development. These AGR fuel experiments will be irradiated over the next ten years to demonstrate and qualify new particle fuel for use in high temperature gas reactors. The experiments, which will each consist of six separate capsules, will be irradiated in an inert sweep gas atmosphere with individual on-line temperature monitoring and control for each capsule. The swept gas will also have on-line fission product monitoring to track performance of the fuel in each individual capsule during irradiation. The design of the first experiment (designated AGR-1) was completed in 2005, and the fabrication and assembly of the test train as well as the support systems and fission product monitoring system that monitor and control the experiment during irradiation were completed in September 2006. The experiment was inserted in the ATR in December 2006, and is serving as a shakedown test of the multi-capsule experiment design that will be used in the subsequent irradiations as well as a test of the early variants of the fuel produced under this program. The experiment test train as well as the monitoring, control, and data collection systems are discussed and the status of the experiment is provided.

INITIAL IRRADIATION OF THE FIRST ADVANCED GAS REACTOR FUEL DEVELOPMENT AND QUALIFICATION EXPERIMENT IN THE ADVANCED TEST REACTOR.

INITIAL IRRADIATION OF THE FIRST ADVANCED GAS REACTOR FUEL DEVELOPMENT AND QUALIFICATION EXPERIMENT IN THE ADVANCED TEST REACTOR. PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

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Book Description
The United States Department of Energy's Advanced Gas Reactor (AGR) Fuel Development and Qualification Program will be irradiating eight separate tri-isotopic (TRISO) particle fuel (in compact form) experiments in the Advanced Test Reactor (ATR) located at the Idaho National Laboratory (INL). These irradiations and fuel development are being accomplished to support development of the next generation reactors in the United States. The ATR has a long history of irradiation testing in support of reactor development and the INL has been designated as the United States Department of Energy's lead laboratory for nuclear energy development. The ATR is one of the world's premiere test reactors for performing long term, high flux, and/or large volume irradiation test programs. These AGR fuel experiments will be irradiated over the next ten years to demonstrate and qualify new particle fuel for use in high temperature gas reactors. The experiments, which will each consist of six separate capsules, will be irradiated in an inert sweep gas atmosphere with individual on-line temperature monitoring and control for each capsule. The swept gas will also have on-line fission product monitoring to track performance of the fuel in each individual capsule during irradiation.

Melting and relocation of fuel in PWR severe accidents - preliminary experiments

Melting and relocation of fuel in PWR severe accidents - preliminary experiments PDF Author: P. D. Parsons
Publisher:
ISBN:
Category :
Languages : en
Pages : 0

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Fuel Element Design and Analysis for Advanced Test

Fuel Element Design and Analysis for Advanced Test PDF Author:
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ISBN:
Category :
Languages : en
Pages :

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The Advanced Test Reactor (ATR), located at the Id.

The Advanced Test Reactor (ATR)

The Advanced Test Reactor (ATR) PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

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Energy Research Abstracts

Energy Research Abstracts PDF Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 464

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