Needs of Advanced Safeguards Technologies for Future Nuclear Fuel Cycle (FNFC) Facilities and a Trial Application of SBD Concept to Facility Design of a Hypothetical FNFC Facility
Creators
- 1. Nuclear Nonproliferation Science and Technology Center, Japan Atomic Energy Agency, Tokai-mura, Ibaraki (Japan)
- 2. Quantum Beam Science Directorate, Japan Atomic Energy Agency, Tokai-mura, Ibaraki (Japan)
- 3. J-PARC Center, Japan Atomic Energy Agency, Tokai-mura, Ibaraki (Japan)
- 4. Quantum Beam Science Directorate, Kizugawa, Kyoto (Japan)
- 5. Research Center for Nuclear Physics, Osaka University, Suita, Osaka (Japan)
Description
Some of future nuclear fuel cycle (FNFC) facilities are supposed to have the characteristic features of very large throughput of plutonium, low decontamination reprocessing (no purification process; existence of certain amount of fission products (FP) in all process material), full minor actinides (MA) recycle, and treatment of MOX with FP and MA in fuel fabrication. In addition, the following international safeguards requirements have to be taken into account for safeguards approaches of the FNFC facilities. -Application of integrated safeguards (IS) approach; -Remote (unattended) verification; - 'Safeguards by Design' (SBD) concept. These features and requirements compel us to develop advanced technologies, which are not emerged yet. In order to realize the SBD, facility designers have to know important parts of design information on advanced safeguards systems before starting the facility design. The SBD concept requires not only early start of R and D of advanced safeguards technologies (before starting preliminary design of the facility) but also interaction steps between researchers working on safeguards systems and nuclear facility designers. The interaction steps are follows. Step-1; researchers show images of advanced safeguards systems to facility designers based on their research. Step-2; facility designers take important design information on safeguards systems into process systems of demonstration (or test) facility. Step-3; demonstration and improvement of both systems based on the conceptual design. Step-4; Construction of a FNFC facility with the advanced safeguards systems We present a trial application of the SBD concept to a hypothetical FNFC facility with an advanced hybrid K-edge densitometer and a Pu NDA system for spent nuclear fuel assembly using laser Compton scattering (LCS) X-rays and γ-rays and other advanced safeguards systems. (author)
Files
42081508.pdf
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Additional details
Identifiers
Publishing Information
- Imprint Title
- Symposium on International Safeguards: Preparing for Future Verification Challenges
- Imprint Pagination
- vp.
- Journal Page Range
- 14 p.
- Report number
- IAEA-CN--184
Conference
- Title
- Preparing for Future Verification Challenges
- Acronym
- Symposium on International Safeguards
- Dates
- 1-5 Nov 2010
- Place
- Vienna (Austria)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 42081508
- Subject category
- S98: NUCLEAR DISARMAMENT, SAFEGUARDS AND PHYSICAL PROTECTION;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPTON EFFECT; DECONTAMINATION; DENSITOMETERS; DESIGN; FISSION PRODUCTS; GAMMA RADIATION; INFORMATION; NUCLEAR FACILITIES; PLUTONIUM; REPROCESSING; SAFEGUARDS; SPENT FUELS; TEST FACILITIES; VERIFICATION; X RADIATION
- Descriptors DEC
- ACTINIDES; BASIC INTERACTIONS; CLEANING; ELASTIC SCATTERING; ELECTROMAGNETIC INTERACTIONS; ELECTROMAGNETIC RADIATION; ELEMENTS; ENERGY SOURCES; FUELS; INTERACTIONS; IONIZING RADIATIONS; ISOTOPES; MATERIALS; MEASURING INSTRUMENTS; METALS; NUCLEAR FUELS; PHOTOMETERS; RADIATIONS; RADIOACTIVE MATERIALS; REACTOR MATERIALS; SCATTERING; SEPARATION PROCESSES; TRANSURANIUM ELEMENTS
Optional Information
- Notes
- 8 refs, 15 figs, 4 tabs
- Secondary number(s)
- IAEA-CN--184/065