High-Dose TL Dosimetry of Reactor Neutrons

Obryk, B.; Malik, Klaudia; Bilski, P.; Igielski, Andrzej; Dankowski, J.; Kurowski, A.; Prokopowicz, R.; Pytel, Krzysztof

doi:10.1093/rpd/ncx244

Cited by 6 publications

(6 citation statements)

References 12 publications

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“…The TLD700 results are not presented since their readout protocol was not suited for such high integrated dose levels. Further study on the TLD700 readout protocol are to be performed, based on work on reading procedures for high dose measurement with LiF:Mg,Cu,P detectors [10]- [12].…”

Section: Conclusion and Outlooksmentioning

confidence: 99%

Gamma-Heating and Gamma Flux Measurements in the JSI TRIGA Reactor: Results and Prospects

Gruel

Ambrožič

Destouches

et al. 2020

IEEE Trans. Nucl. Sci.

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The neutron field of various irradiation positions of the TRIGA Mark II reactor of the Jožef Stefan Institute has been thoroughly characterized by neutron activation dosimetry and miniature fission chambers techniques. In order to have a fully validated calculation scheme to analyze and plan experiments, the gamma field also has to be experimentally validated. The 10-year long collaboration between CEA and JSI is a perfect framework to carry out such a study, and measurements of the gamma field started in late 2016. Several measurement techniques were investigated in in-core and ex-core positions. On-line measurements were carried out using miniature ionization chambers manufactured by the CEA and PTW Farmer ionization chambers. Positional dependence was studied, showing a decrease in the delayed gamma contribution to the total gamma flux with increasing distance from the reactor core center. To characterize the gamma dose in the core, as well as in the periphery, thermo-and optically stimulated luminescent detectors were tested. These detectors are commonly used at CEA to measure the gamma dose in a given material in order to study the nuclear heating in various core elements (control rod, baffle, structural material). Different filters were used in order to assess an integrated dose ranging from a few Gy up to several kGy. The feasibility of such measurements demonstrates the complementarity between measurements with dosimetry and ionization chambers from low to very high gamma-dose environment, such as in material testing reactors.

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Section: Conclusion and Outlooksmentioning

confidence: 99%

Gamma-Heating and Gamma Flux Measurements in the JSI TRIGA Reactor: Results and Prospects

Gruel

Ambrožič

Destouches

et al. 2020

IEEE Trans. Nucl. Sci.

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Section: Conclusion and Outlooksmentioning

confidence: 99%

Gamma-heating and gamma flux measurements in the JSI TRIGA reactor, results and prospects

Gruel

Ambrožič²,

Destouches

et al. 2020

EPJ Web Conf.

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The neutron field of various irradiation positions of the TRIGA Mark II reactor of the Jožef Stefan Institute has been thoroughly characterized by neutron activation dosimetry and miniature fission chambers techniques. In order to have a fully validated calculation scheme to analyze and plan experiments, the gamma field also has to be experimentally validated. The 10-year long collaboration between CEA and JSI is a perfect framework to carry out such a study, and measurements of the gamma field started in late 2016. Several measurement techniques were investigated in in-core and ex-core positions. On-line measurements were carried out using miniature ionization chambers manufactured by the CEA and PTW Farmer ionization chambers. Positional dependence was studied, showing a decrease in the delayed gamma contribution to the total gamma flux with increasing distance from the reactor core center. To characterize the gamma dose in the core, as well as in the periphery, thermo- and optically stimulated luminescent detectors were tested. These detectors are commonly used at CEA to measure the gamma dose in a given material in order to study the nuclear heating in various core elements (control rod, baffle, structural material). Different filters were used in order to assess an integrated dose ranging from a few Gy up to several kGy. The feasibility of such measurements demonstrates the complementarity between measurements with dosimetry and ionization chambers from low to very high gamma-dose environment, such as in material testing reactors.

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“…These materials were exposed to either gamma, neutron or electron beam irradiation and their use as dosimeters for high and very high radiation dose analyzed [37,38,43,[54][55][56][57]. Neutron detection from a nuclear reactor or neutron sources (such as Am-Be or 252 Cf) using thermoluminescence detectors has been a great challenge in radiation dosimetry, and several works have been devoted to investigating this process in the past [58,[63][64][65][66][67][68][69]. Particularly, interaction of thermal and epithermal neutron with matter has awakened special interest in some authors because a larger effective neutron capture cross-section than fast neutrons is found for some nuclides like 10 B and 6 Li [70][71][72].…”

Section: High and Very-high Radiation Dosementioning

confidence: 99%

“…In medical application, boron neutron capture therapy (BNCT) is a method for the treatment of brain tumors in which TLDs detectors can be used to determinate the gamma dose and evaluate the dose due to the charged particles generated in the thermal neutron interaction using consistent kerma factor [62,73]. On the other hand, Obryk et al [69] have mentioned that during the research of radiation damage to electronic components at the Maria research fission reactor, Poland, TL dosimetry using different kinds of MCP and MTS has been performed in order to evaluate the neutron and gamma components of the radiation field during exposure.…”

Section: High and Very-high Radiation Dosementioning

confidence: 99%

“…In a nuclear reactor the neutron field comes accompanied mostly by gamma radiation, however, other different types of particles such as electrons, photons, protons and also heavy-charged particles can be also emitted [67,69]. For instance, LiF TLDs enriched with 6 Li ( 6 LiF, with 95.6 % 6 Li) is sensitive to both neutron and gamma, whilst 7 LiF (with 0.07 % 6 Li) has no response to thermal neutrons [17,29,67,69,80]. Thus, in a mixed radiation field of gamma and thermal neutron field both TLDs can be used, 7 LiF…”

Section: Detection Of Neutrons In a Nuclear Research Reactormentioning

confidence: 99%

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Production of synthetic polycrystals of CaSiO3 and their study as new detectors of gamma radiation, thermal neutrons and accelerated ions.

Lorenzo¹

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Em especial ao prof. Shigueo Watanabe pela sua orientação, paciência, disposição e apoio no desenvolvimento deste trabalho, incentivando a maioria das minhas decisões, agradeço muito. Ao Conselho Nacional de desenvolvimento Científico e Tecnológico (CNPq) pelo apoio financeiro. À Eng. Elizabeth Ribeiro Somessari, ao Eng. Carlos Gaia da Silveira do CTR-IPEN-SP; ao Aldo Oliveira e Vicente de Paulo Campos do GMR-IPEN-SP pelas inúmeras vezes que nos atenderam gentilmente para as irradiações gama realizadas neste trabalho. À Professora Carmen Cecilia Bueno do Centro de Tecnologia das Radiações-IPEN pela ajuda nas irradiações com nêutrons no reator nuclear de pesquisa IEA-R1 do IPEN. Ao Prof. Gundu Rao pela análise das medidas de EPR as quais ajudaram muito no aprimoramento do presente trabalho, e pela ajuda na revisão do inglês. Ao prof. Satoshi Kodaira do Instituto Nacional de Ciências Radiológicas (NIRS) em Chiba-Japão e à Dra. Luana Nascimento do Centro Belga de Pesquisa Nuclear (SCK•CEN) pela ajuda nas irradiações das nossas amostras com prótons e íons de carbono no NIRS. Ao Prof. Sergey Nikiforov e à colega Daria Ananchenko do Instituto de Física e Tecnologia da Universidade Federal dos Urais em Ecaterimburgo-Rússia por me aceitar no seu laboratório como parte de um estágio de pesquisa. ii Ao Dr. Tássio A. Cavalieri do Centro de Engenharia Nuclear do Instituto de Pesquisas Energéticas e Nucleares (CEN-IPEN-SP) pela importante colaboração e ajuda com as simulações de Monte Carlo. À Nancy Kuniko Umisedo do Laboratório de Dosimetria do IFUSP pelas irradiações com raios X. Aos Professores Nilo Cano, René Rojas e Fernando Chubaci pela paciência, compreensão e pela sua disponibilidade para responder às minhas dúvidas no desenvolvimento deste trabalho. À Dra. Roseli Gennari pela ajuda na mistura das amostras e pelas sugestões na produção dos policristais usados neste trabalho. À Edna Toledo pela ajuda e disposição nos processos burocráticos e os muitos momentos agradáveis na hora do café no LACIFID.

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High-Dose TL Dosimetry of Reactor Neutrons

Cited by 6 publications

References 12 publications

Gamma-Heating and Gamma Flux Measurements in the JSI TRIGA Reactor: Results and Prospects

Gamma-Heating and Gamma Flux Measurements in the JSI TRIGA Reactor: Results and Prospects

Gamma-heating and gamma flux measurements in the JSI TRIGA reactor, results and prospects

Production of synthetic polycrystals of CaSiO3 and their study as new detectors of gamma radiation, thermal neutrons and accelerated ions.

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