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• W2570162502 abstract "Previous proliferation resistance and proliferation risk assessments have considered nuclear material through the whole fuel cycle and not specifically focused on spent fuel storage. This project evaluates the proliferation resistance of the three main types of spent fuel storage: spent fuel pool, dry cask storage, and geological repository. The assessment methodology utilizes various intrinsic and extrinsic proliferation resistance attributes for each spent fuel storage type. These attributes are used to calculate a total proliferation resistance (PR) value. The PR values range from 0.00 to 1.00, with a greater number meaning that the facility is more proliferation resistant. Given current data, the spent fuel pool is the most proliferation resistant method for storing spent fuel. The extrinsic attributes, mainly involving safeguards measures, affect the total PR value the most. As a result, several recommendations have been made to improve the proliferation resistance of spent fuel storage. INTRODUCTION & BACKGROUND Increasing energy demands have caused many countries to pursue nuclear power because of the large-scale electricity output that it can provide. The World Nuclear Association estimates that nuclear power capacity will increase from the current worldwide capacity of 367 GW to anywhere from 602 to 1350 GW by 2030 [1]. This means that nuclear power capacity will double or even triple within the next 20 years. Each new power plant presents proliferation risk as it adds special nuclear material to the fuel cycle. Both existing and newly-built nuclear power plants will add more and more special nuclear material to the fuel cycle each year. In order to prevent the diversion of nuclear material to a weapons program, the International Atomic Energy Agency (IAEA) employs safeguards on most of the nuclear material in non-nuclear weapons states (NNWS), as designated by the Treaty on the Non-Proliferation of Nuclear Weapons (NPT). Each NNWS has a specific agreement with the IAEA in regards to safeguarding facilities and material. The goal of IAEA safeguards is to prevent, and failing that, detect the diversion of significant quantities of nuclear material from civilian facilities to nuclear weapons programs. International safeguards thus reduces the proliferation risk of a nuclear power program [2]. The IAEA measures the amount of special nuclear material in terms of significant quantities (SQs), or the estimated amount of that material theoretically needed to create a nuclear weapon. An SQ of plutonium is 8 kg, and an SQ of low-enriched uranium is 75 kg, measured in terms of the contained U-235 [2]. As of the 2010 IAEA Annual Report, there are 172,180 SQs in 674 facilities under safeguards worldwide. Of these facilities, 235 are power reactors. There are 132,505 SQs of plutonium contained in safeguarded reactor core fuel and spent fuel, over 75% of the total SQs under safeguards [3]. The accumulation of spent fuel presents the largest (in terms of the amount of material) proliferation risk in the civilian nuclear fuel cycle. Spent fuel in storage will continue to" @default.
• W2570162502 created "2017-01-13" @default.
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• W2570162502 date "2012-01-01" @default.
• W2570162502 modified "2023-09-23" @default.
• W2570162502 title "Proliferation resistance assessment of various methods of spent nuclear fuel storage and disposal" @default.
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