Transient Reactor Test (TREAT) Facility Design and Experiment Capability

Pope, Chad L.; Jensen, Colby; Gerstner, Douglas M.; Parry, James R.

doi:10.1080/00295450.2019.1599615

Cited by 16 publications

(3 citation statements)

References 5 publications

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“…Used nuclear fuel is a difficult sample for neutron imaging due to the density of the material and the high doses of gamma and neutron radiation being emitted. With the recent restart of the Transient Test Reactor (TREAT) at the Idaho National Laboratory [11,28], there will be an increased need for the abilities of the NRAD facility. It is essential that the neutron beams of the ERS and NRS are characterized to provide sufficient data to users of the facilities.…”

Section: Discussionmentioning

confidence: 99%

Neutron Beam Characterization at Neutron Radiography (NRAD) Reactor East Beam Following Reactor Modifications

Giegel

Craft

Papaioannou

et al. 2021

QuBS

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The Neutron Radiography Reactor at Idaho National Laboratory (INL) has two beamlines extending radially outward from the east and north faces of the reactor core. The control rod withdrawal procedure has recently been altered, potentially changing power distribution of the reactor and thus the properties of the neutron beams, calling for characterization of the neutron beams. The characterization of the East Radiography Station involved experiments used to measure the following characteristics: Neutron flux, neutron beam uniformity, cadmium ratio, image quality, and the neutron energy spectrum. The ERS is a Category-I neutron radiography facility signifying it has the highest possible rank a radiography station can achieve. The thermal equivalent neutron flux was measured using gold foil activation and determined to be 9.61 × 106 ± 2.47 × 105 n/cm2-s with a relatively uniform profile across the image plane. The cadmium ratio measurement was performed using bare and cadmium-covered gold foils and measured to be 2.05 ± 2.9%, indicating large epithermal and fast neutron content in the beam. The neutron energy spectrum was measured using foil activation coupled with unfolding algorithms provided by the software package Unfolding with MAXED and GRAVEL (UMG). The Monte-Carlo N-Particle (MCNP6) transport code was used to assist with the unfolding process. UMG, MCNP6, and measured foil activities were used to determine a neutron energy spectrum which was implemented into the MCNP6 model of the east neutron beam to contribute to future studies.

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Section: Discussionmentioning

confidence: 99%

Neutron Beam Characterization at Neutron Radiography (NRAD) Reactor East Beam Following Reactor Modifications

Giegel

Craft

Papaioannou

et al. 2021

QuBS

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“…Another partial goals are to quantify the impact of pulse width on fuel performance, obtain new data on high burnup fuel under pulse conditions, quantify the additional margin provided by modern cladding alloys to PCMI failure limits and offer improved data for modelers using specially designed tests that eliminate key uncertainties in high-burnup fuel tests [2]. The facilities, that house HERA programme, are TREAT (Transient Reactor Test Facility) reactor and hot cells in Idaho (USA) [3,4] and NSRR (Nuclear Safety Research Reactor) reactor in Japan [5].…”

Section: Introductionmentioning

confidence: 99%

Thermomechanical calculation within the HERA programme

Kinkorová

2023

APP

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HERA (High Burnup Experiments in Reactivity Initiated Accident) is one of the programmes which should replace closed Halden reactor. As the name implies HERA is focused on the tests simulated RIA (Reactivity Initiated Accident) and the aim of the programme is to investigate the performance and behaviour of high burnup fuel in RIA transients. The first phase of HERA programme consists of two steps which are the blind calculation of different RIA scenarios (different pulse width, enthalpy increase, hydrogen content and gap size) and in-reactor test with fresh fuel.The set of thermomechanical calculation was performed with the FRAPTRAN computer code as part of the first phase of HERA. The influence of several parameters on the fuel behaviour was observed, the varying parameters were the pulse width, peak radial average enthalpy increase, hydrogen content and the hydrogen rim size and gap size. In addition, the effect of type and setting of boundary condition was investigated.

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“…This understanding is typically acquired with the use in-pile (i.e., in-core or in-reactor) sensors deployed as part of experiments in Materials Test Reactors (MTRs). MTRs such as the Advanced Test Reactor (ATR) and the Transient Reactor Test Facility at the Idaho National Laboratory use specialized irradiation capsules equipped with in-pile instrumentation for targeted property measurements within the extreme environment of a nuclear reactor core [9][10][11]. Current in-pile instrumentation efforts look to assess, verify, and increase the precision of measurements under irradiation with the development of advanced sensors capable of monitoring temperature, physiochemical conditions, neutron flux/dose, pressure, and multi-physics field properties.…”

Section: Introductionmentioning

confidence: 99%

Additive Manufacturing of Miniaturized Peak Temperature Monitors for In-Pile Applications

Fujimoto

Hone

Manning

et al. 2021

Sensors

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Passive monitoring techniques have been used for peak temperature measurements during irradiation tests by exploiting the melting point of well-characterized materials. Recent efforts to expand the capabilities of such peak temperature detection instrumentation include the development and testing of additively manufactured (AM) melt wires. In an effort to demonstrate and benchmark the performance and reliability of AM melt wires, we conducted a study to compare prototypical standard melt wires to an AM melt wire capsule, composed of printed aluminum, zinc, and tin melt wires. The lowest melting-point material used was Sn, with a melting point of approximately 230 °C, Zn melts at approximately 420 °C, and the high melting-point material was aluminum, with an approximate melting point of 660 °C. Through differential scanning calorimetry and furnace testing we show that the performance of our AM melt wire capsule was consistent with that of the standard melt-wire capsule, highlighting a path towards miniaturized peak-temperature sensors for in-pile sensor applications.

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Transient Reactor Test (TREAT) Facility Design and Experiment Capability

Cited by 16 publications

References 5 publications

Neutron Beam Characterization at Neutron Radiography (NRAD) Reactor East Beam Following Reactor Modifications

Neutron Beam Characterization at Neutron Radiography (NRAD) Reactor East Beam Following Reactor Modifications

Thermomechanical calculation within the HERA programme

Additive Manufacturing of Miniaturized Peak Temperature Monitors for In-Pile Applications

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