Source term calculation and validation for 18F-production with a cyclotron for medical applications at HZDR

Autor: B Naumann, Jörg Konheiser, A. Magin, Stefan E. Müller, A. Ferrari

Publikováno v: Journal of radiological protection, 39 (3), 906–919

In this document we present the calculation and experimental validation of a source term for ${}^{18}$F-production with a cyclotron for medical applications operating at 18 MeV proton energy and 30 $\mu$A proton current. The Monte Carlo codes MCNP6 a

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::c67b2765f9ff6cb4b2ebe7ad256f3299
https://doi.org/10.1088/1361-6498/ab2ae8

Feasibility study for detection of reactor state changes during severe accidents via external gamma radiation measurements

Autor: Carsten Brachem, Uwe Hampel, Jörg Konheiser, R. Rachamin

Publikováno v: Annals of Nuclear Energy. 114:175-180

The gamma radiation field outside of a nuclear reactor carries information about the coolant inventory and the nuclear fuel distribution inside the reactor pressure vessel. Hence, it may serve as an indicator for changes in the reactor internal struc

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::51a235945cbd7df1563313a4caab2add
https://doi.org/10.1016/j.anucene.2017.12.013

Monte Carlo Calculation Procedure and Its Implementation for Radiation Load Estimation on Russian VVER Reactor Equipment

Autor: Jörg Konheiser, Azamat Gazetdinov, Pavel Borodkin, Nikolay Khrennikov, Silvio Baier

Publikováno v: Sixteenth International Symposium on Reactor Dosimetry, 07.-12.05.2017, Santa Fe, USA
Sixteenth International Symposium on Reactor Dosimetry (ISRD-16), 07.-12.05.2017, Santa Fe, USAProceedings of the 16th International Symposium on Reactor Dosimetry, West Conshohocken: ASTM International, 978-0-8031-7661-4, 579-589

A prediction of radiation load parameters (fluence, fluence rate, neutron energy spectrum) of reactor components, e.g. reactor pressure vessel (RPV), of Russian VVER reactors is regulated by the requirements of the Russian normative documents. One of

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::b188d5db630d2fda338230f5ac66767a
https://doi.org/10.1520/stp160820170074

Neutron shielding studies on an advanced molten salt fast reactor design

Autor: Jörg Konheiser, Bruno Merk

Publikováno v: Annals of Nuclear Energy 64(2014), 441-448

The molten salt reactor technology has gained some new interest. In contrast to the historic molten salt reactors, the current projects are based on designing a molten salt fast reactor. Thus the shielding becomes significantly more challenging than

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::f812683ee451f0cb86aaccf6b2c0c5e5
https://doi.org/10.1016/j.anucene.2013.07.014

Shielding and activation calculations around the reactor core for the MYRRHA ADS design

Autor: Stefan E. Mueller, A. Ferrari, Massimo Sarotto, Jörg Konheiser, A. Stankovskiy, D. Castelliti

Publikováno v: ICRS-13 & RPSD-2016, 13th International Conference on Radiation Shielding & 19th Topical Meeting of the Radiation Protection and Shielding Division of the American Nuclear Society-2016, 03.-06.10.2016, Paris, France
EPJ Web of Conferences, Vol 153, p 05001 (2017)
ICRS-13 & RPSD-2016, 13th International Conference on Radiation Shielding & 19th Topical Meeting of the Radiation Protection and Shielding Division of the American Nuclear Society-2016, 03.-06.10.2016, Paris, FranceEPJ Web Conferences, 153 (2017) 05001

In the frame of the FP7 European project MAXSIMA, an extensive simulation study has been done to assess the main shielding problems in view of the construction of the MYRRHA accelerator-driven system at SCK CEN in Mol (Belgium). An innovative method

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::285b11b4f0fb98084f1a0c116b0dba8c
https://www.hzdr.de/publications/Publ-26773-2