Integral modelling of the ITER cooling water systems radiation source for applications outside of the Bio-shield

Pietri, Marco De; Alguacil, J.; Kolsek, Aljaz; Pedroche, G.; Ghirelli, N.; Polunovskiy, E.; Loughlin, M.; Tonqueze, Y. Le; Sanz, J.; Juárez, R.

doi:10.1016/j.fusengdes.2021.112575

Cited by 16 publications

(5 citation statements)

References 9 publications

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“…The safety case will deal with several radiation sources spread all across the entire facility (shown in Figure 1 and Figure 2): (1) plasmas of different species, (2) DD & DT reactions in the NBI components 28 , (3) high-energy particles following runaway electrons events, (4) activated structures and components 39 , (5) activated corrosion products across the Tokamak Cooling Water System (TCWS) 40 , (6) 16 N, 17 N neutron and photon emitters across the TCWS 41 , and (7) activated Tokamak dust impregnating components 42 .…”

Section: Iter Safety Case and The Need For An Integral Representationmentioning

confidence: 99%

“…The 16 N source contained in the TCWS presents a span of 10 orders of magnitude in intensity 41 in an intricate distribution across the entire facility crossing the bioshield. It is known to compete with, or even outpace the plasma source influence in diverse locations beyond the bio-shield in the Tokamak Complex and outside it.…”

Section: Sky-shine Due To Decay Of 16 Nmentioning

confidence: 99%

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ITER full model in MCNP for radiation safety demonstration

Juarez,

Belotti,

Kolšek

et al. 2024

Preprint

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Development of nuclear fusion as a safe and virtually limitless power source receives growing attention in the context of looming energy crisis and climate change. ITER project stands as the flagship international project and advances steadily. Construction of the Tokamak Complex is nearly finished, and the assembly of core components has started in the site. In parallel, design is getting finalized and the safety case gets more concrete. Current approaches for radiation safety demonstration based in 3D nuclear analysis require sophisticated artifacts due to the consideration of separate MCNP models for the Tokamak and the rest of the facility, resulting in cumbersome studies and thus, debilitated conclusions. To improve this situation, we have built the first integral MCNP model of the ITER facility: the ITER full model. Accompanied by improvements to the D1SUNED code, we illustrate its computational practicality and pertinence in two meaningful simulations for ITER safety case. This work represents the culmination of a two-decades-long effort of ITER modelling seeking to demonstrate the radiation safety. Beyond supporting the remaining design tasks, this model represents a noticeable simplification in the approach to produce the corresponding 3D nuclear analysis. It improves the robustness of the first-of-a-kind ITER safety case.

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Section: Iter Safety Case and The Need For An Integral Representationmentioning

confidence: 99%

Section: Sky-shine Due To Decay Of 16 Nmentioning

confidence: 99%

ITER full model in MCNP for radiation safety demonstration

Juarez,

Belotti,

Kolšek

et al. 2024

Preprint

Self Cite

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“…mainly alpha particles and neutrons. The main in-vessel components are the First Wall-Blanket 6 (FW-BLK) [17,18] and the divertor 7 (DIV) [19,20]. Additional in-vessel components are the In-Vessel Coils (IVCs), mounted on the Vacuum Vessel 8 (VV) surface right behind the FW-BLK, the Diagnostics and Auxiliary Heating Systems installed in the equatorial and upper ports.…”

Section: Description Of the Ibed Loopmentioning

confidence: 99%

“…Recent work performed in the framework of the Nuclear Integration Engineering (NIE) program [6] highlighted that the major impact on the ORE relates to activities on the primary cooling systems. Consequently, the need to update the ACPs source term for future analyses remains a crucial objective [7]. The ITER Radiation, Safety and Environment (RSE) group decided to re-evaluate the inventory of ACPs.…”

Section: Introductionmentioning

confidence: 99%

Use of the OSCAR-Fusion V1.4.a code for a preliminary assessment of the ACP contamination within the main ITER water cooling circuit

Carloni,

Dacquait,

Polunovskiy

et al. 2024

Nucl. Fusion

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One of the main objectives of ITER is to produce 500 MW of power from a D-T plasma for several seconds. This goal presents two inherent challenges: firstly, in-vessel components will require active cooling to remove the heat coming from the fusion reaction (i.e., mainly fast neutrons and alpha particles). Secondly, the materials exposed to the neutron flux will yield activated corrosion products (ACPs) in all primary cooling circuits of ITER. From a safety point of view, ACPs are one of the contributors to the Occupational Radiological Exposure (ORE), they represent a source of radiological waste and also contribute to the source term for accidental scenarios involving the loss of primary confinement. Therefore, ACPs assessment is key to estimate radiological impact for nuclear workers and the public. ITER nuclear safety engineers adopted OSCAR-Fusion v1.4.a code to assess the ACPs inventory in the Integrated Blanket ELMs and Divertor (IBED) cooling loop. This paper describes the selection of input data, the modelling of the circuits and the operational scenarios used in OSCAR-Fusion calculations. This study also examines the outcomes of such calculations, notably in terms of ACPs inventory, emphasizing the impact on the ORE and highlighting its driving parameters. Furthermore, this paper provides recommendations for better ACPs management in the context of the ITER project and in accordance with the ALARA principle

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“…Numerous computational analyses of the water activation process have been performed for ITER and DEMO. However, the results are subject to uncertainties and are therefore of poor quality due to the lack of experimental nuclear data, inaccurate computational methods/codes and experimental facilities to validate the methodology experimentally, specifically considering timeand spatial dependent radiation sources (such as the flow of activated water in the cooling system [2]). Consequently, the calculated dose rates are subject to larger uncertainties.…”

Section: Introductionmentioning

confidence: 99%

Assessment of the gamma and neutron dose field around the closed-water activation loop at the JSI TRIGA reactor

Kotnik,

Snoj,

Lengar

2023

EPJ Web Conf.

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A closed-water activation loop is being built at the Jožef Stefan Institute TRIGA reactor in Slovenia to serve as a well-defined and stable source of high-energy gamma rays and neutrons. The radial piercing port, which penetrates the graphite reflector and touching the reactor core was chosen for the installation of the closed-water loop due to the high neutron flux and favourable shielding conditions of the surrounding concrete bioshield. The main objective of this work is to assess the neutron and gamma dose field outside the port to obtain important details for the final design of the inner part of the irradiation facility and to assess the background noise for the detectors. The main part of the work consists of the design of the shielding plugs and the construction of a detailed MCNP model of the whole irradiation facility. The dose field calculations were performed with a two-step hybrid transport approach using ADVANTG for variance reduction and MCNP for particle transport. Such deep penetration and shielding calculations are challenging and computationally intensive. The results showed that the dose rate using shielding plugs is more than 7 orders of magnitude lower compared to an empty open port. To reduce the computational uncertainty, further optimisation of the ADVANTG input is essential. The final design of the shielding plugs is described. Additional lead shielding blocks will be added outside the port afterwards if needed.

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Integral modelling of the ITER cooling water systems radiation source for applications outside of the Bio-shield

Cited by 16 publications

References 9 publications

ITER full model in MCNP for radiation safety demonstration

ITER full model in MCNP for radiation safety demonstration

Use of the OSCAR-Fusion V1.4.a code for a preliminary assessment of the ACP contamination within the main ITER water cooling circuit

Assessment of the gamma and neutron dose field around the closed-water activation loop at the JSI TRIGA reactor

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