IAEA Symposium on International Safeguards

Session

[NEW] The Safeguards Challenges of New and Advanced Reactors

6 Nov 2018, 11:00

M Building (Vienna International Centre)

276. Advanced Reactor Design – Ensuring Excellence in Non-Proliferation and Security

Dr Anita Nilsson (AN&Associates)

Preparing for safeguards new facilities, processes and campaigns (NEW)

Wedge Participant

Advanced nuclear reactor technology is presently being developed in several countries with prototype reactors being tested. Several factors are driving forward international interest in advanced nuclear reactors including climate change and the urgent need to reduce carbon emission globally by mid-century, rising energy requirements in industrializing economy nations, and the applicability of...

230. Alternative Fuel cycle Materials Verification and Monitoring Using Advanced High-Dose Neutron Detectors

Dr Daniela Henzlova (Los Alamos National Laboratory)

Preparing for safeguards new facilities, processes and campaigns (NEW)

Wedge Participant

The development of advanced sustainable nuclear fuel cycles relying on used nuclear fuel is one of the key programs pursued by the United States Department of Energy to minimize waste generation, limit proliferation risk and maximize energy production using nuclear energy. Safeguarding of advanced nuclear fuel cycles is essential to ensure the safety and security of the nuclear material yet it...

63. Challenges and Notional Solutions for the Application of Agency Safeguards on Transportable Small Modular Reactors

Dr J. Stephen Adams (U.S. Department of State)

Preparing for safeguards new facilities, processes and campaigns (NEW)

Wedge Participant

IAEA safeguards for light water power reactors (LWRs) allow inspectors to provide the international community with a high degree of confidence that nuclear material located at the reactor site has not been diverted to nuclear weapons, other nuclear explosive devices, or purposes unknown. IAEA safeguards for sealed, transportable small modular reactors (SMR), however, are not as well-developed...

247. Design solutions for nuclear transportable power plants with SMRs to facilitate the application of the IAEA safeguards and support the nonproliferation regime

Mr Vladimir Galitskikh (JSC "Afrikantov OKBM")

Preparing for safeguards new facilities, processes and campaigns (NEW)

Wedge Participant

With the growing demand for electricity, there is an increasing interest in designs of small reactor plants, which enable the power supply to a consumer in areas remote from large electric grids as well as reduction of production costs. The orientation towards the use of such reactors in foreign countries stimulates Russian developers to search for technical solutions aimed at facilitating...

102. FAST REACTORS, FUEL CYCLES, AND PROBLEM OF NUCLEAR NONPROLIFERATION

Dr Alexander Chebeskov (SSC IPPE)

Preparing for safeguards new facilities, processes and campaigns (NEW)

Wedge Participant

For 60 years of its existence, world nuclear power has passed a long way in its development and has reached a wide geographical spread. Currently there is quite intensive effort to development of nuclear power technology of IV generation having better nuclear safety and economical features. Among these technologies, there are innovative nuclear energy technologies based on fast neutron...

243. High Temperature Gas Cooled Reactor with Pebble Fuel -Its Accountancy and Verification

Mr QIANG MIAO (China Institute of Atomic Energy)

Preparing for safeguards new facilities, processes and campaigns (NEW)

Wedge Participant

The HTR with pebble fuel is a typical reactor of generation IV nuclear energy system and a module facility in China will be commissioning in the coming years. China had offered the facility to implement safeguard by the agency. This paper will discuss an approach for the accountancy system based on the module facility and, also, develop some of the verification scenery to support the domestic...

178. International Safeguards for Microreactors: Opportunities and Challenges for the International Atomic Energy Agency

Mr Robert Otto (Pacific Northwest National Laboratory)

Preparing for safeguards new facilities, processes and campaigns (NEW)

Wedge Participant

The last 15 years have witnessed increased investment in small-modular reactors (SMRs) as a cost-effective, flexible, and potentially safer alternative to large-scale nuclear generation. Part of this trend has been renewed interest in a sub-category of ultra-small SMRs known as microreactors, which produce no more than 10 MWe. Many microreactor designs embrace novel features or operation...

132. Molten Salt Fast Reactor in Generation IV: Proliferation challenges

Prof. Victor Ignatiev (NRC “Kurchatov Institute”, Moscow, the Russian Federation)

Preparing for safeguards new facilities, processes and campaigns (NEW)

Wedge Participant

Within the Generation-IV International Forum (GIF), research is performed on the molten salt reactor (MSR) concepts. Two fast spectrum MSR are being studied, which are large power units with homogeneous core: the two fluid 3000MWt MSFR in France, Euratom and Switzerland as well as the single fluid 2400 MWt MOSART in RF. R&D studies are on-going in order to verify that fast spectrum MSR systems...

84. Molten Salt Reactors and Associated Safeguards Challenges and Opportunities

Mr Andrew Worrall (Oak Ridge National Laboratory)

Preparing for safeguards new facilities, processes and campaigns (NEW)

Wedge Participant

Molten Salt Reactors (MSRs) were first proposed at Oak Ridge National Laboratory (ORNL) shortly after World War II to power military aircraft and were followed by the development of civilian MSR programs also at ORNL from the mid-1950s to the mid-1970s. Although the development of the concepts ended in the late-1970s, a wide variety of new MSR technologies are now being developed and are...

2. MYRRHA Safeguards Approach by Design

Dr Didier De Bruyn (Belgian Nuclear Research Centre (SCK•CEN))

Preparing for safeguards new facilities, processes and campaigns (NEW)

Wedge Participant

Once started as a small irradiation facility, which was already based on the accelerator-driven system concept and had a dedicated objective to produce radioisotopes for medical purposes, the purpose of our MYRRHA programme is to demonstrate the ADS concept at pre-industrial scale, to demonstrate transmutation and - as the reactor is a fast neutron source – to also serve as a flexible...

248. Nonproliferation Aspects for Transportable Nuclear Plant Lifecycle

Mr Gennady Pshakin (IPPI)

Preparing for safeguards new facilities, processes and campaigns (NEW)

Wedge Participant

New trend in development of nuclear energy use is small modular reactors (SMR) as energy source for remote regions. Special directions in those trends take innovation projects of transportable nuclear power plants (TNPP) with factory fueled and sealed core, having resources for exploitation for 10 years without reloading and without storage for spent nuclear fuel at the site. Such nuclear...

151. On the Correlations of Burnup and Material Amounts in PB-HTR Material Accounting

Dr Bing Xia (Institute of Nuclear and New Energy Technology, Tsinghua University)

Preparing for safeguards new facilities, processes and campaigns (NEW)

Wedge Participant

The pebble bed high temperature reactors (PB-HTR) presents new challenges for the nuclear safeguards and material accounting. From the point of view of material accounting, the most important issue is to determine the amounts of the key material isotopes such as the isotopes of uranium and plutonium. Since there is no practical isotope examination on the irradiated fuel elements of PB-HTR by...

152. Proliferation resistance and safeguardability of very high temperature reactor

Dr TOMOOKI SHIBA (Integrated Support Center for Nuclear Nonproliferation and Nuclear Security, Japan Atomic Energy Agency)

Preparing for safeguards new facilities, processes and campaigns (NEW)

Wedge Participant

Since the accident at Fukushima Daiichi Nuclear Power Plant on March 2011, the reliance on nuclear energy has been decreased. The Very High Temperature Reactor (VHTR) has its inherent safety, enabling mass production of hydrogen for the future hydrogen-based society as well as the power generation. Development plans for practical application of VHTR have been rapid since the Fukushima disaster...

89. Protactinium presents a challenge for safeguarding thorium reactors

Dr Eva Uribe (Sandia National Laboratories)

Preparing for safeguards new facilities, processes and campaigns (NEW)

Wedge Participant

Since their conception in the 1950s, thorium reactors have been pursued as safer and cleaner alternatives to uranium-fueled reactors. Thorium fuel cycles have the potential to be more proliferation resistant compared to traditional uranium-plutonium fuel cycles, as they could produce less weapons usable plutonium, and the fissile U-233 generated will be protected by co-production of the highly...

107. Safeguard challenges and consideration on nuclear safeguards for HTR-PM

Mr Jiong Guo (INET, Tsinghua University)

Preparing for safeguards new facilities, processes and campaigns (NEW)

Wedge Participant

The high temperature reactor-pebble bed modular(HTR-PM) is the first commercial demonstration nuclear power plant of modular HTR under construction in the world. And it is expected to be commissioned by the end of 2018. As a new type of nuclear power plant, on one hand, the safeguard of the nuclear plant will adopt the measures, such as isolation, which are effective for the safeguard of the...

293. Safeguards Challenges and Safeguards Technology Needs Assessment for Leading Thorium Fuel Cycles

Dr Louise Worrall (Oak Ridge National Laboratory)

Preparing for safeguards new facilities, processes and campaigns (NEW)

Wedge Participant

Several thorium fuel cycle variants are currently being actively pursued by the global nuclear energy community. These variants have short-, medium-, and long-term deployment pathways in a variety of reactor types, including thorium-fueled molten salt reactors. Those pathways in turn give rise to a variety of fuel designs, fuel cycle facilities, and nuclear material processing requirements....

127. The Gen-IV Proliferation Resistance and Physical Protection methodology applied to GEN IV system designs: some reflections

Dr Giacomo G.M. Cojazzi (European Commission, Joint Research Centre, Directorate G - Nuclear Safety and Security)

Preparing for safeguards new facilities, processes and campaigns (NEW)

Wedge Participant

The Generation Four International Forum (GIF) formed a proliferation resistance and physical protection (PR&PP;) Working Group (PRPPWG) to develop a methodology to evaluate the six GIF nuclear energy systems concepts.
The PRPPWG developed the methodology through a series of development and demonstration case studies, using a hypothetical “Example Sodium Fast Reactor” (ESFR). The ESFR...

114. Wet Solid Radioactive Waste and Shielding as Alternate Detective Measures

Ms Duaa AlJilani (Jordan Atomic energy Commission)

Preparing for safeguards new facilities, processes and campaigns (NEW)

Wedge Participant

Research reactors with thermal power of 25 MW or less are assumed not able to produce 1 SQ of Pu or U-233 per annum. Binford’s correlation is a rough estimate for the capability of any Uranium-fueled thermal reactor to produce Pu. The quality of Pu-239 varies with fresh fuel type, neutron flux and irradiation time. An increase in irradiation time results in the build-up of Pu-240.

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