Neutron transmission experiment with PTFE at AKR-2

J 2025

Neutron transmission experiment with PTFE at AKR-2

KOSTAL, Michal; Marek ZMESKAL; Tomas CZAKOJ; Juan Jose Gomez RODRIGUEZ; Marco VIEBACH et al.

Základní údaje

Originální název

Neutron transmission experiment with PTFE at AKR-2

Autoři

Vydání

ANNALS OF NUCLEAR ENERGY, OXFORD, PERGAMON-ELSEVIER SCIENCE LTD, 2025, 0306-4549

Další údaje

Jazyk

angličtina

Typ výsledku

Článek v odborném periodiku

Obor

10300 1.3 Physical sciences

Stát vydavatele

Velká Británie a Severní Irsko

Utajení

není předmětem státního či obchodního tajemství

Odkazy

URL

Impakt faktor

Impact factor: 2.300 v roce 2024

Označené pro přenos do RIV

Ano

Kód RIV

RIV/00216224:14330/25:00143695

Organizační jednotka

Fakulta informatiky

Klíčová slova anglicky

Transmission experiment; Neutron wide beam; Research reactor; Deep neutron transport; Neutron cross sections for fluorine; AKR-2 reactor

Změněno: 2. 4. 2026 16:12, RNDr. Pavel Šmerk, Ph.D.

Anotace

V originále

Fluorine is a crucial element for the nuclear industry and technology due to its application in nuclear fuel production as uranium hexafluoride (UF6), its use of Teflon (R) in criticality experiments, and its use in coolant/ fuel materials in several Molten Salt Reactor (MSR) concepts currently being designed. There have been many efforts to improve the neutron reaction cross sections for fluorine. The neutron broad-beam transmission experiment through the PTFE (PolyTetraFluoroEthylene) block at the Dresden AKR-2 reactor has been performed to validate existing evaluated cross-section libraries from 1 to 10 MeV of incident neutron energies. Calculations with studied data sets (ENDF/B-VIII.0, INDEN, JEFF-3.3, and JENDL-5) show satisfactory agreement with the experiment in the energy region above 2.1 MeV within the uncertainty range. The measured neutron transmission shows a systematic disagreement in a calculation to experiment comparison in the energy region 1-2.1 MeV. This behavior is consistent with the measured 252Cf(s.f.) neutron leakage in the PTFE block with dimensions of 60 x 50 x 50 cm. Improvement of evaluated cross sections below 2 MeV of neutron incident energy is needed.

Citovat

KOSTAL, Michal; Marek ZMESKAL; Tomas CZAKOJ; Juan Jose Gomez RODRIGUEZ; Marco VIEBACH; Alexander KNOSPE; Vincent MELZER; Sascha WEICHEL; Carsten LANGE; Antonio HURTADO; Evzen LOSA; Jan SIMON; Stanislav SIMAKOV; Martin SCHULC; Evzen NOVAK; Tomas PELTAN; Zdeněk MATĚJ a Roberto CAPOTE. Neutron transmission experiment with PTFE at AKR-2. ANNALS OF NUCLEAR ENERGY. OXFORD: PERGAMON-ELSEVIER SCIENCE LTD, 2025, roč. 224, č. 224, s. 1-13. ISSN 0306-4549. Dostupné z: https://doi.org/10.1016/j.anucene.2025.111741.

@article{2553989,
   author = {Kostal, Michal and Zmeskal, Marek and Czakoj, Tomas and Rodriguez, Juan Jose Gomez and Viebach, Marco and Knospe, Alexander and Melzer, Vincent and Weichel, Sascha and Lange, Carsten and Hurtado, Antonio and Losa, Evzen and Simon, Jan and Simakov, Stanislav and Schulc, Martin and Novak, Evzen and Peltan, Tomas and Matěj, Zdeněk and Capote, Roberto},
   article_location = {OXFORD},
   article_number = {224},
   doi = {https://doi.org/10.1016/j.anucene.2025.111741},
   keywords = {Transmission experiment; Neutron wide beam; Research reactor; Deep neutron transport; Neutron cross sections for fluorine; AKR-2 reactor},
   language = {eng},
   issn = {0306-4549},
   journal = {ANNALS OF NUCLEAR ENERGY},
   title = {Neutron transmission experiment with PTFE at AKR-2},
   url = {https://www.sciencedirect.com/science/article/abs/pii/S0306454925005584},
   volume = {224},
   year = {2025}
}

TY  - JOUR
ID  - 2553989
AU  - Kostal, Michal - Zmeskal, Marek - Czakoj, Tomas - Rodriguez, Juan Jose Gomez - Viebach, Marco - Knospe, Alexander - Melzer, Vincent - Weichel, Sascha - Lange, Carsten - Hurtado, Antonio - Losa, Evzen - Simon, Jan - Simakov, Stanislav - Schulc, Martin - Novak, Evzen - Peltan, Tomas - Matěj, Zdeněk - Capote, Roberto
PY  - 2025
TI  - Neutron transmission experiment with PTFE at AKR-2
JF  - ANNALS OF NUCLEAR ENERGY
VL  - 224
IS  - 224
SP  - 1-13
EP  - 1-13
PB  - PERGAMON-ELSEVIER SCIENCE LTD
SN  - 03064549
KW  - Transmission experiment
KW  - Neutron wide beam
KW  - Research reactor
KW  - Deep neutron transport
KW  - Neutron cross sections for fluorine
KW  - AKR-2 reactor
UR  - https://www.sciencedirect.com/science/article/abs/pii/S0306454925005584
N2  - Fluorine is a crucial element for the nuclear industry and technology due to its application in nuclear fuel production as uranium hexafluoride (UF6), its use of Teflon (R) in criticality experiments, and its use in coolant/ fuel materials in several Molten Salt Reactor (MSR) concepts currently being designed. There have been many efforts to improve the neutron reaction cross sections for fluorine. The neutron broad-beam transmission experiment through the PTFE (PolyTetraFluoroEthylene) block at the Dresden AKR-2 reactor has been performed to validate existing evaluated cross-section libraries from 1 to 10 MeV of incident neutron energies. Calculations with studied data sets (ENDF/B-VIII.0, INDEN, JEFF-3.3, and JENDL-5) show satisfactory agreement with the experiment in the energy region above 2.1 MeV within the uncertainty range. The measured neutron transmission shows a systematic disagreement in a calculation to experiment comparison in the energy region 1-2.1 MeV. This behavior is consistent with the measured 252Cf(s.f.) neutron leakage in the PTFE block with dimensions of 60 x 50 x 50 cm. Improvement of evaluated cross sections below 2 MeV of neutron incident energy is needed.
ER  -

KOSTAL, Michal; Marek ZMESKAL; Tomas CZAKOJ; Juan Jose Gomez RODRIGUEZ; Marco VIEBACH; Alexander KNOSPE; Vincent MELZER; Sascha WEICHEL; Carsten LANGE; Antonio HURTADO; Evzen LOSA; Jan SIMON; Stanislav SIMAKOV; Martin SCHULC; Evzen NOVAK; Tomas PELTAN; Zdeněk MATĚJ a Roberto CAPOTE. Neutron transmission experiment with PTFE at AKR-2. \textit{ANNALS OF NUCLEAR ENERGY}. OXFORD: PERGAMON-ELSEVIER SCIENCE LTD, 2025, roč.~224, č.~224, s.~1-13. ISSN~0306-4549. Dostupné z: https://doi.org/10.1016/j.anucene.2025.111741.

Přehled o publikaci