Evaluation of the Radiation Effects of Residents Living Around the NSRI Under the External Hazards

2018 ◽  
Author(s):  
Yuiko Motome ◽  
Yoshiya Akiyama ◽  
Murao Hiroyuki
Keyword(s):  
Radiation Effects ◽  
Research Reactor ◽  
Science Research ◽  
Nuclear Fuels ◽  
Pulse Reactor ◽  
Research Reactors ◽  
Nuclear Science ◽  
Safety Research ◽  
Fukushima Daiichi ◽  
Reactor Type

The NSRR (Nuclear Safety Research Reactor) is a research reactor of TRIGA-ACPR (Annular Core Pulse Reactor) type, located in the Nuclear Science Research Institute (NSRI). The NSRR facility has been utilized for fuel irradiation experiments to study the behaviors of nuclear fuels under reactivity initiated accident (RIA) conditions. Under the new regulation standards after the Fukushima Daiichi accident, the research reactors are being regulated according to the risk of the facility. Graded approach is introduced in the regulation. In order to apply the graded approach, the radiation effects of residents living around the NSRI under the external hazards were evaluated and the level of the risk of the NSRR facility was investigating. This report is summarized for the result of the evaluation in case the safety functions were lost by the tornado, earthquake and following tsunami. As the result, the risk is confirmed to be low, since the effective dose of the residents has been below 5 mSv per event due to the loss of the safety functions by the tornado, earthquake and following tsunami.

scholarly journals Innovative and safe supply of fuels for reactors

2020 ◽  
Vol 6 ◽  
pp. 40
Author(s):  
Stéphane Valance ◽  
Bruno Baumeister ◽  
Winfried Petry ◽  
Jan Höglund
Keyword(s):  
Power Plant ◽  
Nuclear Power ◽  
High Performance ◽  
Research Reactor ◽  
Fissile Material ◽  
Nuclear Fuels ◽  
Research Reactors ◽  
Enriched Uranium ◽  
Performance Research ◽  
And Training

Within the Euratom research and training program 2014–2018, three projects aiming at securing the fuel supply for European power and research reactors have been funded. Those three projects address the potential weaknesses – supplier diversity, provision of enriched fissile material – associated with the furbishing of nuclear fuels. First, the ESSANUF project, now terminated, resulted in the design and licensing of a fuel element for VVER-440 nuclear power plant manufactured by Westinghouse. The HERACLES-CP project aimed at preparing the conversion of high performance research reactor to low enriched uranium fuels by exploring fuels based on uranium-molybdenium. Finally, the LEU-FOREvER pursues the work initiated in HERACLES-CP, completing it by an exploration of the high-density silicide fuels, and including the diversification of fuel supplier for soviet designed European medium power research reactor. This paper describes the projects goals, structure and their achievements.

Evaluation of Radiation Effects on Residents Living Around the NSRR Under External Hazards

2020 ◽  
Vol 6 (2) ◽  
Author(s):  
Yuiko Motome ◽  
Yoshiya Akiyama ◽  
Hiroyuki Murao
Keyword(s):  
Radiation Effects ◽  
Research Reactor ◽  
Reactor Core ◽  
Fission Products ◽  
Internal Exposure ◽  
Spent Fuel ◽  
Loss Of Function ◽  
Safety Research ◽  
Spent Fuel Storage ◽  
Fuel Storage

Abstract The nuclear safety research reactor (NSRR) is a research reactor of training research isotopes general atomics—annular core pulse reactor (TRIGA-ACPR) type, located in the Nuclear Science Research Institute (NSRI). The NSRR facility has been utilized for fuel irradiation experiments to study the behaviors of nuclear fuels under reactivity-initiated accident (RIA) conditions. Under the new regulation standards, which was established after the Fukushima Daiichi accident, research reactors are regulated based on the risk of the facilities. The graded approach is introduced in the regulation. To apply the graded approach, the radiation effects on residents living around the NSRR under the external hazards were evaluated, and the level of the risk of the NSRR facility was investigated. This paper summarizes the result of the evaluation in the case where the safety functions are lost due to a tornado, an earthquake followed by a tsunami. There is fuel in the reactor core, fresh fuel storage, and spent fuel storage. As the effects from reactor core, we evaluate the external exposure to radiation and exposure from the release of fission products assuming that loss of function to shut down the reactor, break of cladding tubes, loss of reactor pool water, and collapse of the reactor building. As the effects from fresh fuel storage, we evaluate the internal exposure assuming that the fresh fuel particles released into the air because of breaking into pieces. In addition, we evaluate the critical safety assuming that the critical safety shapes of the fresh fuel storage are lost. As the effects from spent fuel storage, we evaluate the critical safety assuming that the critical safety shapes of the spent fuel storage are lost. All in all, the risk is confirmed to be relatively low, since the effective dose on the residents is found to be below 5 mSv per event due to the loss of the safety functions caused by the tornado, earthquake, and the accompanying tsunami.

Decommissioning of AECL Whiteshell Laboratories

2009 ◽  
Author(s):  
Grant W. Koroll ◽  
Dennis M. Bilinsky ◽  
Randall S. Swartz ◽  
Jeff W. Harding ◽  
Michael J. Rhodes ◽  
...  
Keyword(s):  
Waste Management ◽  
Research Reactor ◽  
Nuclear Research ◽  
Nuclear Facilities ◽  
Safety Research ◽  
Final Design ◽  
The Government ◽  
Government Of Canada ◽  
High Level ◽  
Waste Handling

Whiteshell Laboratories (WL) is a Nuclear Research and Test Establishment near Winnipeg, Canada, operated by AECL since the early 1960s and now under decommissioning. WL occupies approximately 4400 hectares of land and employed more than 1000 staff up to the late-1990s, when the closure decision was made. Nuclear facilities at WL included a research reactor, hot cell facilities and radiochemical laboratories. Programs carried out at the WL site included high level nuclear fuel waste management research, reactor safety research, nuclear materials research, accelerator technology, biophysics, and industrial radiation applications. In preparation for decommissioning, a comprehensive environmental assessment was successfully completed [1] and the Canadian Nuclear Safety Commission issued a six-year decommissioning licence for WL starting in 2003 — the first decommissioning licence issued for a Nuclear Research and Test Establishment in Canada. This paper describes the progress in this first six-year licence period. A significant development in 2006 was the establishment of the Nuclear Legacy Liabilities Program (NLLP), by the Government of Canada, to safely and cost effectively reduce, and eventually eliminate the nuclear legacy liabilities and associated risks, using sound waste management and environmental principles. The NLLP endorsed an accelerated approach to WL Decommissioning, which meant advancing the full decommissioning of buildings and facilities that had originally been planned to be decontaminated and prepared for storage-with-surveillance. As well the NLLP endorsed the construction of enabling facilities — facilities that employ modern waste handling and storage technology on a scale needed for full decommissioning of the large radiochemical laboratories and other nuclear facilities. The decommissioning work and the design and construction of enabling facilities are fully underway. Several redundant non-nuclear buildings have been removed and redundant nuclear facilities are being decontaminated and prepared for demolition. Along with decommissioning of redundant structures, site utilities are being decommissioned and reconfigured to reduce site operating costs. New waste handling and waste clearance facilities have been commissioned and a large shielded modular above ground storage (SMAGS) structure is in final design in preparation for construction in 2010. The eventual goal is full decommissioning of all facilities and infrastructure and removal of stored wastes from the site.

scholarly journals Supporting infrastructures and research reactors: status, needs and international cooperation, IAEA ICERR (International CEntres based on Research Reactors) and IGORR (International Group on Research Reactors), FP7 and H2020 JHR access rights

2020 ◽  
Vol 6 ◽  
pp. 26
Author(s):  
Gilles Bignan ◽  
Jean-Yves Blanc
Keyword(s):  
Turning Point ◽  
Research Reactor ◽  
Project Proposal ◽  
Joint Project ◽  
Research Reactors ◽  
International Group ◽  
Access Rights ◽  
Evolving Context ◽  
Set Up ◽  
Under Construction

The panorama of research reactors in the world is at a turning point, with many old ones being shutdown, a very few new ones under construction and many newcomer countries interested to get access to one or to build one domestic research reactor or zero-power reactor. In this evolving context, several actions have been set up to answer this international collaboration need: the IAEA has launched the ICERR initiative, the OECD/NEA is proposing the P2M joint project proposal. In France, the Jules Horowitz Reactor (JHR), under construction at CEA Cadarache, within an International Consortium, will be one of the few tools available for the industry and research in the next decades. The paper presents some update of its construction, its experimental capacities and the European support through FP7 and H2020 tools. This paper provides also some insights of international tools (ICERR, P2M) and about the International Group on Research Reactors (IGORR) and how they complement or interact with the JHR.

Investigation on the Accident of Loss of Offsite Power of CARR

2010 ◽  
Author(s):  
Qing Lu ◽  
Suizheng Qiu ◽  
Wenxi Tian ◽  
Guanghui Su
Keyword(s):  
Research Reactor ◽  
Natural Circulation ◽  
Circulation Flow ◽  
Hydraulic Simulation ◽  
Research Reactors ◽  
Structure Changes ◽  
Two Peaks ◽  
Vertical Height

A code has been developed with proper models for the thermal-hydraulic simulation of research reactors, and the accident of loss of offsite power of CARR (the China Advanced Research Reactor) has been analyzed. It is found that the transient can be departed into four parts with two peaks, and at last terminated to a natural circulation state. Furthermore, in order to investigate the effect of the height of the in core structures during this accident, several structure changes have been proposed and analyzed. It is demonstrated that the increase of the vertical height of the in core structures not always do help to decreasing the peak temperatures and increasing the natural circulation flow in the transient.

Safeguarding Atoms for Peace

1966 ◽  
Vol 60 (1) ◽  
pp. 34-54 ◽  
Author(s):  
Mason Willrich
Keyword(s):  
Nuclear Weapons ◽  
Nuclear Fuels ◽  
Nuclear Science ◽  
Economic Use ◽  
Remarkable Progress

Since 1945 the number of nations possessing nuclear weapons has increased five times and stockpiles of nuclear weapons have increased thousands of times. The enormity of the build-up of capabilities for nuclear destruction has largely overshadowed the remarkable progress that has been made since 1945 in developing the peaceful applications of nuclear science. The take-off point for the economic use of nuclear fuels for generating electricity appears to have now been reached.

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