Human factors engineering and participatory design in the project of a nuclear research reactor control centre

The Human Factors Engineering (HFE) program is an essential aspect for the design of nuclear installations. The overall aim of the HFE program is the improvement of the operational reliability and safety of plant operation. The HFE program main purpose is to ensure that human factor practices are incorporated into the plant design, emphasizing man-machine interface issues and design improvement of the nuclear reactor Control Centre. The Control Centre of nuclear reactor is a combination of control rooms, control suites and local control stations, which are functionally connected and located on the reactor site. The objective of this paper is to present a participatory design approach, including human factor issues, for the Control Centre of a nuclear research reactor used to produce radioisotopes and for nuclear research. The design approach is based on participatory design principles, using human factor standards, ergonomic guidelines, and the participation of a multidisciplinary team during all design phases. Using the information gathered, an initial sketch 3D of the Control Centre was developed.

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State of the Art of Nuclear Reactor Instrument Automation

Journal of Dynamic Systems Measurement and Control ◽

10.1115/1.3426835 ◽

1974 ◽

Vol 96 (4) ◽

pp. 394-398

Author(s):

M. Taeschner ◽

R. Gariod

Keyword(s):

High Performance ◽

Nuclear Reactor ◽

Research Reactor ◽

State Of The Art ◽

Nuclear Research ◽

Automation System ◽

Nuclear Research Reactor ◽

High Investment

Due to its complexity, nuclear reactor instrument automation is a challenge to engineers. High investment and running costs of a nuclear research reactor imply the use of advanced equipment and concepts for instrument automation when striving for high performance, reliability, and operational convenience under budgetary pressure. The article describes a successfully operating instrument automation system stressing the important underlying concepts trying to avoid too much details on specific hardware which is dependent on the time when one must order things.

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Reevaluation of Spectral Parameters and Neutron Fluxes in IC-7 Irradiation Channel of TRIGA MARK I IPR-R1 Research Nuclear Reactor

Journal of Nuclear Engineering and Radiation Science ◽

10.1115/1.4051249 ◽

2021 ◽

Author(s):

Radojko Jacimovic ◽

Maria Angela de Barros Correia Menezes

Keyword(s):

Nuclear Reactor ◽

Epithermal Neutron ◽

Research Reactor ◽

Nuclear Research ◽

Irradiation Channel ◽

Spectral Parameters ◽

K0 Method ◽

Nuclear Research Reactor ◽

Research Nuclear Reactor ◽

The Stability

Abstract The core configuration of the TRIGA MARK I IPR-R1 nuclear research reactor, Brazil, has been modified six times since the first criticality and the neutron fluxes have been determined using experimental and semi theoretical methodologies determining the neutron fluxes in different irradiation channels and devices, applying different procedures and materials. This reactor operates at 100 kW, however, after new configuration for 250 kW in 2001, the carousel no longer rotates during irradiations aiming at preserving the rotation mechanism. In 2003, the spectral parameters were determined experimentally by the "Cd-ratio for multi-monitor" in five specific channels aiming at the application of NAA k0-standardized method. The determinations were repeated applying the same procedure in 2016, 2018 and 2019. Values for thermal and epithermal neutron fluxes as well as f and a spectral parameters were determined. The experimental results for CRM BCR-320R were calculated by the k0-method of NAA, using the spectral parameters for irradiation channel IC-7 obtained in 2003, 2016, 2018 and 2019 and evaluated by En-score. The values showed that the differences in the results compared to those in 2003 were lower than 2.5%, inside the uncertainty of the method. It shows that the k0-method installed in CDTN is reliable and useful for various purposes. The results of the spectral parameter f presented small differences, in a period of 16 years, pointing out the stability of operation of the reactor TRIGA MARK I IPR-R1.

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Search for neutron-hidden neutron interbrane transitions with MURMUR, a low-noise neutron passing-through-walls experiment

EPJ Web of Conferences ◽

10.1051/epjconf/201921907004 ◽

2019 ◽

Vol 219 ◽

pp. 07004

Author(s):

Coraline Stasser ◽

Michaél Sarrazin ◽

Guy Terwagne

Keyword(s):

Cross Section ◽

Nuclear Reactor ◽

Research Reactor ◽

Nuclear Research ◽

Elastic Cross Section ◽

Low Noise ◽

Beyond The Standard Model ◽

Important Concern ◽

The Standard Model ◽

Nuclear Research Reactor

Multi-braneworld universe is at the heart of many scenarios of physics beyond the Standard Model and the cosmological model ΛCDM. It is thus an important concern to constrain these scenarios which also allow for experiments below the GeV scale. MURMUR is a new neutron passing-through-walls experiment designed to constrain neutron-hidden neutron transitions in the context of braneworlds scenarios. As our visible universe could be a 3-brane embedded in a multidimensional bulk, adjacent hidden 3-branes are often expected. Their existence can be constrained as matter exchange between braneworlds must occur with a swapping probability p. A neutron n can convert into a hidden neutron n′ when scattered by a nucleus with cross section σ(n → n′) ∝ σE(n → n)p, where σE is the usual elastic cross-section. Hidden neutrons could therefore be generated in the moderator medium of a nuclear reactor, where high-flux neutrons undergo many elastic collisions. All the theoretical and technological keys of this experiment soon to be installed at the nuclear research reactor BR2 (SCK.CEN, Mol, Belgium) are introduced.

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Thermal-hydraulically calculation for the Dalat nuclear research reactor

Vietnam Journal of Mechanics ◽

10.15625/0866-7136/10261 ◽

1991 ◽

Vol 13 (4) ◽

pp. 14-19

Author(s):

Ngo Phu Khang

Keyword(s):

Nuclear Reactor ◽

Research Reactor ◽

Nuclear Research ◽

Core Domain ◽

The Core ◽

Nuclear Research Reactor

This paper concerns with thermal-hydraulically calculation for the core domain of the Dalat nuclear reactor in the nominal regime of works. On the base of this calculation some conclusions. On thermal safely of the reactor are conducted.

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Anthropogenic Releases of Radiocarbon and its Concentration Burden in Environment

Current Physical Chemistry ◽

10.2174/1877946809666191011160437 ◽

2020 ◽

Vol 10 (1) ◽

pp. 23-32

Author(s):

Abdul Ghaffar ◽

Zainab Hafeez ◽

Syeda Maria Ali

Keyword(s):

Wind Direction ◽

Nuclear Reactor ◽

Research Reactor ◽

Climatic Factors ◽

Nuclear Research ◽

Prevailing Wind ◽

Prevailing Wind Direction ◽

Pee Dee ◽

Nuclear Research Reactor ◽

Vegetation Samples

: The radiocarbon (14C) concentrations in air and vegetation samples around a nuclear research reactor were studied. Objective: 14C concentrations in the air and vegetation samples around the nuclear research reactor were measured to assess its 14C burden on the environment. Methods: Air samples were collected by converting CO2 into Na2CO3 by using a specified system. Leaf samples were carbonized to convert organic carbon into inorganic carbonates. The samples were converted into carbamate through carbosorb systems with 74% efficiency. The fractionation of 14C for each sample was corrected and normalized to a 13C composition of -25‰ Pee Dee Belemnite. Results: 14C concentrations in the air and vegetation samples around the nuclear research reactor were found to range from 158 to 406 Bq/Kg and 162 to 339 Bq/kgC, respectively. The highest concentrations of 14C were found in the samples close to the reactor and along the prevailing wind direction. The specific activities of the samples decreased with an increase in the distance from the reactor and in the opposite to prevailing wind direction. In addition to the distance from the reactor and wind direction, the local Suess effect was an additional factor affecting the 14C activities in the air and vegetation samples. Conclusion: One can conclude that other than the 14C emissions from the nuclear reactor, local Suess effects and climatic factors (wind directions) dilute and disperse 14C concentrations in the atmosphere and consequently decrease its availability for uptake and accumulation by plants at 4-5 km aerial distance from the point of release in prevailing wind direction.

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Production of Radioisotopes and Radiopharmaceuticals at the Dalat Nuclear Research Reactor

Nuclear Science and Technology ◽

10.53747/jnst.v4i1.213 ◽

2014 ◽

Vol 4 (1) ◽

pp. 46-56

Author(s):

Van Dong Duong ◽

Ngoc Dien Pham ◽

Van Cuong Bui ◽

Phuoc Tho Mai ◽

Thi Thu Nguyen ◽

...

Keyword(s):

Quality Control ◽

Production Rate ◽

Nuclear Reactor ◽

Research Reactor ◽

Operation Time ◽

Nuclear Research ◽

Radioisotope Production ◽

Production Lines ◽

Nuclear Research Reactor ◽

Production Programme

After reconstruction, the Dalat Nuclear Research Reactor (DNRR) was inaugurated on March 20th, 1984 with the nominal power of 500 kW. Since then the production of radioisotopes and labelled compounds for medical use was started. Up to now, DNRR is still the unique one in Vietnam. The reactor has been operated safely and effectively with the total of about 37,800 hrs (approximately 1,300 hours per year). More than 90% of its operation time and over 80% of its irradiation capacity have been exploited for research and production of radioisotopes. This paper gives an outline of the radioisotope production programme using the DNRR. The production laboratory and facilities including the nuclear reactor with its irradiation positions and characteristics, hot cells, production lines and equipment for the production of Kits for labelling with 99mTc and for quality control, as well as the production rate are mentioned. The methods used for production of 131I, 99mTc, 51Cr, 32P, etc. and the procedures for preparation of radiopharmaceuticals are described briefly. Status of utilization of domestic radioisotopes and radiopharmaceuticals in Vietnam is also reported.

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