ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
Latest Magazine Issues
Mar 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
April 2024
Nuclear Technology
Fusion Science and Technology
February 2024
Latest News
iLAMP: Neutron Absorber Material Monitoring for Spent Fuel Pools
The spent fuel pool at TVA’s Watts Bar nuclear power plant near Spring City, Tenn. (Photo: TVA)
Neutron absorber materials are used by nuclear power plants to maintain criticality safety margins in their spent nuclear fuel pools. These materials are typically in the form of fixed panels of a neutron-absorbing composite material that is placed within the fuel pools. (A comprehensive review of such materials used in wet storage pools and dry storage has been provided by the Electric Power Research Institute (EPRI) [1]).
With increasing plant life, there is a need to maintain or establish a monitoring program for neutron absorber materials—if one is not already in place—as part of aging management plans for reactor spent fuel pools.
Such monitoring programs are necessary to verify that the neutron absorbers continue to provide the criticality safety margins relied upon in the criticality analyses of a reactor’s spent fuel pool. To do this, the monitoring program must be capable of identifying any changes to the material and quantifying those changes. It should be noted that not all the changes (for example minor pitting and blistering of the absorber material) will result in statistically or operationally significant impact on the criticality safety margins.
For monitoring neutron absorber materials in spent fuel pools, until recently, two alternatives existed—coupon testing and in situ measurements. A third option, called industry-wide learning aging management program (i-LAMP), was proposed by EPRI and is currently in the final stages of the regulatory review. The following sections describe these monitoring approaches.
S. Grünhagen et al.
Fusion Science and Technology | Volume 54 | Number 1 | July 2008 | Pages 55-58
Technical Paper | Iter and Fusion | doi.org/10.13182/FST08-A1764
Articles are hosted by Taylor and Francis Online.
Detritiation of highly tritium contaminated carbon and metal material used as first wall armour is a key issue for fusion machines like JET and ITER. Re-deposited carbon and hydrogen in the form of flakes and dust can lead to a build-up of the tritium inventory and therefore this material must be removed and processed. The high tritium concentration of the flake and dust material collected from the JET vacuum vessel makes it unsuitable for direct waste disposal without detritiation. A dedicated facility to process the tritiated carbon flake material and recover the tritium has been designed and built. In several test runs active material was successfully processed and detritiated in the new facility. Samples containing only carbon and hydrogen isotopes have been completely oxidized without any residue. Samples containing metallic impurities, e.g. beryllium, require longer processing times, adjusted processing parameters and yield an oxide residue. The detritiation factor was 2 x 104. In order to simulate in-vessel and ex-vessel detritiation techniques, the detritiation of a carbon flake sample by isotopic exchange in a hydrogen atmosphere was investigated. 2.8 % of tritium was recovered by this means.