Metamorphosis of a 35 Year-Old TRIGA Reactor into a Modern BNCT Facility

Auterinen, Iiro; Hiismäki, Pekka; Kotiluoto, Petri; Rosenberg, Rolf; Salmenhaara, Seppo; Seppälä, Tiina; Serén, Tom; Tanner, Vesa; Aschan, Carita; Kortesniemi, Mika; Kosunen, A; Lampinen, Juha; Savolainen, Sauli; Toivonen, M; Välimäki, Petteri

doi:10.1007/978-1-4615-1285-1_36

Cited by 38 publications

(18 citation statements)

References 3 publications

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“…Dosimetry measurements were carried out under conditions pertinent to therapy by the MIT NCT group using the epithermal neutron beams at the Joint Research Centre of the European Commission ͑JRC͒, Petten ͑The Netherlands͒, 10 Nuclear Research Institute ͑NRI͒, Rez ͑Czech Republic͒, 11 VTT Espoo ͑Finland͒, 12 and Studsvik, Nyköping ͑Sweden͒. 13 At each center measurements were performed in a rectangular water-filled phantom having minimum linear dimensions of 40͑W͒ ϫ 40͑H͒ ϫ 20͑D͒ cm 3 that was aligned with the largest side facing the beam aperture.…”

Section: Iia Measurementsmentioning

confidence: 99%

An international dosimetry exchange for BNCT Part II: Computational dosimetry normalizations

et al. 2008

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The meaningful sharing and combining of clinical results from different centers in the world performing boron neutron capture therapy (BNCT) requires improved precision in dose specification between programs. To this end absorbed dose normalizations were performed for the European clinical centers at the Joint Research Centre of the European Commission, Petten (The Netherlands), Nuclear Research Institute, Rez (Czech Republic), VTT, Espoo (Finland), and Studsvik, Nyköping (Sweden). Each European group prepared a treatment plan calculation that was bench-marked against Massachusetts Institute of Technology (MIT) dosimetry performed in a large, water-filled phantom to uniformly evaluate dose specifications with an estimated precision of +/-2%-3%. These normalizations were compared with those derived from an earlier exchange between Brookhaven National Laboratory (BNL) and MIT in the USA. Neglecting the uncertainties related to biological weighting factors, large variations between calculated and measured dose are apparent that depend upon the 10B uptake in tissue. Assuming a boron concentration of 15 microg g(-1) in normal tissue, differences in the evaluated maximum dose to brain for the same nominal specification of 10 Gy(w) at the different facilities range between 7.6 and 13.2 Gy(w) in the trials using boronophenylalanine (BPA) as the boron delivery compound and between 8.9 and 11.1 Gy(w) in the two boron sulfhydryl (BSH) studies. Most notably, the value for the same specified dose of 10 Gy(w) determined at the different participating centers using BPA is significantly higher than at BNL by 32% (MIT), 43% (VTT), 49% (JRC), and 74% (Studsvik). Conversion of dose specification is now possible between all active participants and should be incorporated into future multi-center patient analyses.

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Section: Iia Measurementsmentioning

confidence: 99%

An international dosimetry exchange for BNCT Part II: Computational dosimetry normalizations

et al. 2008

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“…The reactor started operation in 1962 with 100 kW power and the power was upgraded to 250 kW in 1967. The reactor experienced major changes in the mid-1990s, when the graphite of the thermal column was replaced with FLUENTAL moderator (30% Al, 69% AlF 3 1% LiF), developed at VTT, to provide an optimal epithermal flux for Boron Neutron Capture Therapy (BNCT) treatments [4]. At the same time the loading of the reactor was changed such that the fuel rods closest to the BNCT facility were replaced with stainless steel cladded rods with 12% uranium content, resulting in a tilted flux distribution in the reactor and a maximal epithermal flux at the BNCT facility.…”

Section: Fir 1 Reactormentioning

confidence: 99%

Validating the Serpent Model of FiR 1 Triga Mk-II Reactor by Means of Reactor Dosimetry

Viitanen

Leppänen

2016

EPJ Web of Conferences

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Abstract.A model of the FiR 1 Triga Mk-II reactor has been previously generated for the Serpent Monte Carlo reactor physics and burnup calculation code. In the current article, this model is validated by comparing the predicted reaction rates of nickel and manganese at 9 different positions in the reactor to measurements. In addition, track-length estimators are implemented in Serpent 2.1.18 to increase its performance in dosimetry calculations. The usage of the track-length estimators is found to decrease the reaction rate calculation times by a factor of 7-8 compared to the standard estimator type in Serpent, the collision estimators. The differences in the reaction rates between the calculation and the measurement are below 20%.

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“…The reactor is entirely above ground and is surrounded by a concrete shield structure, as shown in Originally, FiR 1 reactor has had a 1.2x1.2x1.7 meters graphite thermal column extending from the outer surface of the reflector assembly and penetrating the reactor tank and shield structure. In 1995-1996, the thermal column was replaced by an epithermal boron neutron capture therapy (BNCT) beam [5]. A BNCT irradiation room was also built of steel tube elements filled with density-optimized heavy concrete and a heavy steel framed lead door.…”

Section: Introductionmentioning

confidence: 99%

Preliminary Waste Characterization Measurements in FiR 1 TRIGA Research Reactor Decommissioning Project

et al. 2018

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The objective of the study has been to verify the calculated residual activity in the decommissioning waste of TRIGA Mark II type research reactor FiR 1 in Finland. The knowledge of radioactive inventory of irradiated materials is important in the planning of the decommissioning activities and is essential for predicting the radiological impact to personnel and environment. Measurements are performed for low active material samples from outer parts of the reactor. Methods include gamma spectrometric measurements, composition measurements with mass spectrometry, oxidation measurements of especially C-14 in graphite and full combustion measurements of lithium enriched shielding materials. Results are compared to estimates calculated with a combined Monte Carlo model of the reactor and a point-depletion code modelling the irradiation history. Decommissioning waste consists mainly of ordinary concrete, aluminium, steel and graphite parts. Only preliminary measurements of low active samples are reported so far, but the same methods will be used later for characterizing and classifying dismantling waste. Some discussion of characterization requirements and future sampling is also included.

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Metamorphosis of a 35 Year-Old TRIGA Reactor into a Modern BNCT Facility

Cited by 38 publications

References 3 publications

An international dosimetry exchange for BNCT Part II: Computational dosimetry normalizations

An international dosimetry exchange for BNCT Part II: Computational dosimetry normalizations

Validating the Serpent Model of FiR 1 Triga Mk-II Reactor by Means of Reactor Dosimetry

Preliminary Waste Characterization Measurements in FiR 1 TRIGA Research Reactor Decommissioning Project

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