Credible accident analyses for TRIGA and TRIGA-fueled reactors

Hawley, S.C.; Kathren, R.L.

doi:10.2172/5330309

Cited by 3 publications

(2 citation statements)

References 4 publications

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“…The same conclusions were found for the same type of reactor operated elsewhere by Hawley and Kathren. 2,5,[24][25][26] For the more stable atmospheric conditions, the maximum TED value decreases to a lower value due to less plume depletion (Fig. 4).…”

Section: Doses Calculationmentioning

confidence: 98%

Comparative Radiation Dose Study of a Hypothetical Accident in a Research Reactor

Dahia¹,

Merrcoche²,

Dadda³

et al. 2022

Kemija U Industriji

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This study is a contribution for radiation dose calculations of a hypothetical accident of a 1 MW research reactor Triga Mark II using HotSpot code. A postulated accidental release of noble gases and halogens were considered. The total effective dose (TED) was estimated for 1 day and 50 years after release. The total damage of fuel element cladding with a maximum radioactivity was considered. The obtained results show minimal TED values at the beginning of the release and at a shorter distance from the source. The maximum calculation results are acceptable and below the recommended public dose limit.

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Section: Doses Calculationmentioning

confidence: 98%

Comparative Radiation Dose Study of a Hypothetical Accident in a Research Reactor

Dahia¹,

Merrcoche²,

Dadda³

et al. 2022

Kemija U Industriji

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“…For a sense of scale, testing in the 1960s included a pulse test in which a reactivity insertion of $5.50 caused the TRIGA Mark F reactor to reach a power level of 6.4 GW, while the fuel reached a maximum temperature of about 660 °C [2]. According to NUREG-2387, 304 stainless steel cladding failure or melting of the U-ZrH 1.6 fuel cannot occur in a TRIGA reactor, and the only credible accident scenario that could result in fuel failure would have to be produced by some large external force during fuel handling [11]. The safety limits and performance of U-ZrH 1.6 fuel are independent of uranium content up to 45 wt% uranium, and the behavior of 8.5-30 wt% uranium fuel is indistinguishable [5].…”

Section: U-zrhx Fuel In Triga Reactorsmentioning

confidence: 99%

MARVEL Reactor Fuel Performance Report

Evans

Keiser

Sweet

2023

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The Microreactor Applications Research Validation and EvaLuation (MARVEL) project is producing a high temperature liquid metal-cooled nuclear test bed at the Idaho National Laboratory (INL) to ultimately improve integration of microreactors to end-user applications. This ambitious effort seeks to design, authorize, construct, test, and operate the reactor within five years. In order to construct and operate the MARVEL reactor in a timely manner, the system will utilize materials and component designs which have already been used, qualified, or licensed from previous reactors. The MARVEL reactor will be located at the INL Transient Reactor Test (TREAT) facility in the north high-bay equipment pit and will use the existing 304 stainless steel-clad U-ZrH 1.6 pin-type fuel system developed by General Atomics and purchased from TRIGA International. This fuel has been previously qualified under the United States Department of Energy's Reduced Enrichment for Research and Test Reactors (RERTR) Program.Even though the regulator of the MARVEL reactor is the United States Department of Energy, the standards and approach recommended by the Nuclear Regulatory Commission is well-defined and utilized here. Following NUREG-1537 regulatory guidance, this report documents the authorization case for the MARVEL fuel system's application to MARVEL and establishes stable and predictable fuel performance during the most thermophysically unfavorable conditions achievable in the MARVEL reactor. To that end, this report provides a comprehensive survey of the known thermophysical properties, performance, and quantitative relationships associated with the MARVEL reactor fuel element and uses this information to determine its mechanical integrity and risk of reaching unacceptable conditions during the most extreme accident scenarios predicted for the reactor using the most conservative assumptions available. The information contained herein is compiled from a combination of historical reports and peer reviewed scientific publication manuscripts. Known mechanisms under which the fuel is susceptible to failure are highlighted and compared to conditions that could exist in the MARVEL reactor during an unanticipated transient or accident scenario.The two scenarios considered for analysis in this report are (1) an unprotected loss of flow accident and (2) a hypothetical unprotected loss of coolant accident during the loss of flow accident. Preliminary 2D steady-state analyses herein indicate that both fuel-cladding chemical interactions and fuel-cladding mechanical interactions are negligible throughout the fuel's operational cycle under both normal and high temperature accident scenario conditions. Although higher fidelity 3D time-dependent modeling and simulations are planned, the following may be concluded presently. The MARVEL fuel element maintains its geometric stability and structural integrity during the most extreme accident scenarios predicted for the MARVEL reactor. The hoop stress during the unprotected loss of flow accident reaches a...

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