Application of Cdznte Detectors for Control of Initial Enrichment of Fresh Nuclear Fuel at Refueling
Creators
- 1. Odessa National Polytechnic University, Odessa, 65044,Shevchenko Ave. 1 (Ukraine)
Description
The task of determining the initial enrichment of nuclear fuel (NF) at nuclear power plants in real time is relevant for both economic indicators of operation of the power unit and for all components of nuclear safety (nuclear safety, security and safeguards). The technology used by nuclear fuel cycle companies is not suitable for use at nuclear power plants. It is proposed to use a measuring system based on CdZnTe semiconductor detectors designed to control the burn-up depth of nuclear fuel for estimating the initial enrichment of fresh nuclear fuel in fuel assemblies (FA). The initial enrichment is estimated with help of the gamma radiation of uranium isotopes of fresh nuclear fuel. A distinctive feature of the system that has been developed is the use of passive tomography technology to take into account the self-absorption of radiation in the FA. The promise of the proposed method for estimating initial enrichment is confirmed by experimental measurements and simulation results. It is shown that the system developed makes it possible to determine the enrichment of nuclear fuel, taking into account its profiling by the volume of FA. Also, the results of measurements confirmed the possibility of using the proposed technical solutions for CdZnTe detectors to create portable monitoring systems for special nuclear material in the field. The solution of this task is of great importance for national security. Key words: CdZnTe detectors / gamma-ray imaging / gamma-ray spectroscopy / special nuclear materials monitoring
Availability note (English)
Available from https://www.epj-conferences.org/articles/epjconf/pdf/2020/01/epjconf_animma2019_03002.pdf; https://doaj.org/article/b3d31912aa9b4b1d931fd884fa9acb50Additional details
Identifiers
Publishing Information
- Journal Title
- EPJ. Web of Conferences
- Journal Volume
- 225
- Journal Page Range
- vp.
- ISSN
- 2100-014X
Conference
- Title
- International Conference on Advancements in Nuclear Instrumentation Measurement Methods and their Applications
- Acronym
- ANIMMA 2019
- Dates
- 17-21 Jun 2019
- Place
- Portoroz (Slovenia)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 53115991
- Subject category
- S46: INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; CDZNTE SEMICONDUCTOR DETECTORS; COMPUTERIZED SIMULATION; DESIGN; FUEL ASSEMBLIES; FUEL CYCLE; GAMMA RADIATION; GAMMA SPECTROSCOPY; MEASURING METHODS; NUCLEAR FUELS; NUCLEAR POWER PLANTS; RADIATION MONITORING; RADIATION PROTECTION; REACTOR OPERATION; SELF-ABSORPTION; TOMOGRAPHY; URANIUM ISOTOPES
- Descriptors DEC
- ABSORPTION; DIAGNOSTIC TECHNIQUES; ELECTROMAGNETIC RADIATION; ENERGY SOURCES; FUELS; IONIZING RADIATIONS; ISOTOPES; MATERIALS; MEASURING INSTRUMENTS; MONITORING; NUCLEAR FACILITIES; OPERATION; POWER PLANTS; RADIATION DETECTORS; RADIATIONS; REACTOR LIFE CYCLE; REACTOR MATERIALS; SEMICONDUCTOR DETECTORS; SIMULATION; SORPTION; SPECTROSCOPY; THERMAL POWER PLANTS