Restarting the Transient Reactor Test (TREAT) Facility Reactor for Nuclear Transient Testing Science: A Special Issue of <i>Nuclear Technology</i>

Bumgardner, J.D.; Wachs, Daniel M.

doi:10.1080/00295450.2019.1650605

Cited by 5 publications

(3 citation statements)

References 0 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…TREAT offers the unique flexibility to serve many fuel and reactor designs by enabling a modular experiment strategy, as well as a highly agile control rod system for tailoring desired power histories for experiments [9]. Special experimental devices have been (and are currently) under development to aid in performing integral LOCA experiments and related separate-effects studies [10].…”

Section: Treat and The Treat Loca Devicementioning

confidence: 99%

Combined TREAT-LOC and SATS LOCA Experiment Plan: Integral LOCA Experiments on High-Burnup Fuels

Armstrong,

Jensen,

Folsom

et al. 2022

View full text Add to dashboard Cite

IntroducConThe Transient Reactor Test Facility (TREAT) loss-of-coolant (LOC) and high-burnup (HBu) experiment series, along with the Severe Accident Test StaUon (SATS) HBu experiment series, are integral LOC accident (LOCA) experiments planned under DOE's AFC program. These experiments aim to support burnup extension needs by addressing idenUfied R&D prioriUes in order to achieve an improved understanding of HBu fuel fragmentaUon, relocaUon, and dispersal (FFRD) during LOCA events. Data generated under this plan will be used to further validate and confirm exisUng models and inform future R&D and model development.* Fuel length will be limited to the distance between grid spacers, or would include a grid spacer if present in the commercial irradia8on (likely applicable for 50-cm-long specimens in TREAT). Most semi-integral furnace tests have been conducted on segments with a length of nearly 30 cm.

show abstract

Section: Treat and The Treat Loca Devicementioning

confidence: 99%

Combined TREAT-LOC and SATS LOCA Experiment Plan: Integral LOCA Experiments on High-Burnup Fuels

Armstrong,

Jensen,

Folsom

et al. 2022

View full text Add to dashboard Cite

show abstract

“…18,19 When evaluating the FOMs and design considerations for the ATF campaign, there are numerous requirements that must be taken into consideration. 11 The requirements that influence the design of a test vehicle include Leveraging on these requirements, the transient testing program has successfully deployed seven variants of a vehicle design in TREAT since its restart to date. The device is referred to as the minimal activation retrievable capsule holder (MARCH) irradiation vehicle system.…”

Section: Review Of Previous Treat Vehicle Designsmentioning

confidence: 99%

“…Accident Tolerant Fuels (ATF) program, and efforts to license next-generation advanced reactors. 11,12 The TREAT reactor is an air-cooled reactor fueled by uranium-oxide particles dispersed in blocks of graphite placed within zirconium alloy canisters to comprise a square lattice configuration of fuel assemblies. In the central fuel assembly locations, select assemblies can be removed and test vehicles and instrumentation can be inserted in place.…”

Section: Introductionmentioning

confidence: 99%

Developing Separate Effects Transient Test Experiments Using an Out-of-Pile Flowing Water Loop

et al. 2020

View full text Add to dashboard Cite

In 2017 the Transient Reactor Test (TREAT) Facility was restarted after having been placed in a standby state in 1994. The TREAT reactor's restart has since enabled the progressive development of new nuclear technologies within the United States that previously were outsourced to other countries. While the reactor's restart was a large feat worthy of recognition, the experimental use of its characteristics has required further development of an in-pile experimental infrastructure sufficient to support programmatic needs. This hardware has taken the form of capsule designs (compact and elongated) as well as loop concepts representing the phenomena of interest for a subset of the separate effects tests desired for each respective testing campaign. The transient testing program has been a large integrated effort that aligns with the U.S. Department of Energy's current needs. This study complements those programmatic elements by developing, fabricating, and demonstrating a full-scale flowing water loop in an out-of-pile environment. The goal of this effort is to develop a pragmatic understanding of the engineering capabilities and limitations associated with geometric form factors, metering technology, and controls logic under the representative thermal-hydraulic conditions that would be experienced within the TREAT reactor during an in-pile reactivity-initiated accident test. The outcomes of this study result in an evaluation of the conceptual design of a comprehensive flowing water loop, including objective figures of merit for comparing unique instrumentation and the basis for their selection during operations. These efforts directly contribute to and are required for the further advancement of transient testing capabilities within the United States.

show abstract

Lead borate@polydopamine core–shell particles chemically bonded with silicone rubber for neutron and γ‐rays shielding

Zhang

et al. 2021

J of Applied Polymer Sci

View full text Add to dashboard Cite

Rubber composites with excellent radiation shielding and flexibility are extremely important to personal protective equipments (PPEs) for protecting workers from radiation hazards, especially for mixed radiations. It is, however, challenging to achieve uniform dispersion of fillers and good compatibility of the interfaces in highly‐filled rubber composites that are closely related to their physical properties. In this article, lead borate@polydopamine (PBO@PDA) core–shell particles are chemically bonded with silicone rubber (SR) for co‐shielding of neutron and γ‐rays. Uniform dispersion of the core–shell particles and good compatibility of the interfaces give rise to enhanced flexibility of the rubber composites. Particularly, the SR composite with 40 wt% PBO particles displays increases of 106% in elongation at break and 490% in tensile strength to neat SR. Furthermore, the mass attenuation coefficient of γ‐rays (105 KeV) reaches 2.35 and the thermal neutron absorption rate (0.025 eV) of is 76.9%. This work takes into account the balance between radiation shielding and flexibility of rubber composites, which provides a facile strategy to fabricate excellent integrated properties of flexible materials for shielding mixed neutron and γ‐rays.

show abstract

Restarting the Transient Reactor Test (TREAT) Facility Reactor for Nuclear Transient Testing Science: A Special Issue of Nuclear Technology

Cited by 5 publications

References 0 publications

Combined TREAT-LOC and SATS LOCA Experiment Plan: Integral LOCA Experiments on High-Burnup Fuels

Combined TREAT-LOC and SATS LOCA Experiment Plan: Integral LOCA Experiments on High-Burnup Fuels

Developing Separate Effects Transient Test Experiments Using an Out-of-Pile Flowing Water Loop

Lead borate@polydopamine core–shell particles chemically bonded with silicone rubber for neutron and γ‐rays shielding

Contact Info

Product

Resources

About