Position evaluation of ex-core neutron flux measurement in new type graphite reactors
Creators
- 1. University of West Bohemia, Faculty of Electrical Engineering, Univerzitni 8, 30100 Pilsen (Czech Republic)
- 2. Research Center Rez, Hlavni 130, Rez, 250 68 Husinec (Czech Republic)
- 3. Czech Institute of Informatics, Robotics and Cybernetics, Jugoslavskych partyzanu 1580/3, 160 00 Prague (Czech Republic)
Description
Several concepts of new reactors use graphite. Some of them use graphite as a moderator, some of them as a reflector. There are at least two concepts of these graphitetype reactors under development in the Czech Republic. Both reactors use graphite as the reflector. An in-core measurement might be impossible to use because of various reasons, for instance, high temperature or aggressive environment. Therefore, this article focuses on ex-core neutron flux measurement system placed in the graphite reflector and the optimization of ex-core detector position. A set of experiments were performed at LR-0 reactor. The LR-0 is a light water reactor with a well-defined neutron field, which can be used for different material insertion tests and testing of its influence on criticality. Several modifications of LR-0 cores were modelled in Monte Carlo codes Serpent and KENO. A set of calculations were performed for verification of the criticality and neutron flux course in the reactor core and graphite reflector. Further investigation was focused on the influence of the presence of a graphite reflector on the neutron distribution in the reactor core. The LR-0 graphite experiments were also used to verify the calculations. Based on the results of this article, the optimal position of ex-core detectors in the graphite reflector is proposed. Key words: ex-core measurement / neutron flux / graphite reflector / Serpent / KENO
Availability note (English)
Available from https://www.epj-conferences.org/articles/epjconf/pdf/2021/07/epjconf_animma2021_05005.pdf; https://doaj.org/article/731cb433b7bf44f09109fb2c01dfbb56Additional details
Identifiers
Publishing Information
- Journal Title
- EPJ. Web of Conferences
- Journal Volume
- 253
- Journal Page Range
- vp.
- ISSN
- 2100-014X
Conference
- Title
- International Conference on Advancements in Nuclear Instrumentation Measurement Methods and their Applications
- Acronym
- ANIMMA 2021
- Dates
- 21-25 Jun 2021
- Place
- Prague (Czech Republic)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 53090398
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CRITICALITY; GRAPHITE; LR-0 REACTOR; MODERATORS; MONTE CARLO METHOD; NEUTRON FLUX; NEUTRONS; OPTIMIZATION; REACTOR CORES; TESTING; VERIFICATION
- Descriptors DEC
- BARYONS; CALCULATION METHODS; CARBON; ELEMENTARY PARTICLES; ELEMENTS; EXPERIMENTAL REACTORS; FERMIONS; HADRONS; MINERALS; NONMETALS; NUCLEONS; POOL TYPE REACTORS; RADIATION FLUX; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZERO POWER REACTORS