Kazuo Arie

Design of the 4S Reactor

Abstract The Super-Safe, Small and Simple (4S) sodium-cooled fast reactor plant incorporates innovative design features, such as a nonrefueling reactor, passive safety, low maintenance requirements, and inherent security. Major components such as the reflector drive mechanisms, the electromagnetic pumps, and the double-wall tube steam generator have been optimized for efficient and safe operation. The nonrefueling reactor concept is made possible by incorporating a 30-yr refueling interval for the reflector-controlled metallic fuel core. Sodium-cooled, metallic-fueled fast reactors have a good conversion ratio due to fast neutron usage, thus extending the core life. Passive safety is achieved with redundant residual heat removal systems that function using only natural circulation, and a metallic core with a negative reactivity coefficient. Low maintenance requirements are achieved by simplifying the design and minimizing the use of active components, and by using electromagnetic pumps, which have no moving parts. The inherent security of the nuclear materials is significantly enhanced by the nonrefueling reactor concept and the minimal maintenance requirements. In addition, the reactor building is located below ground level, providing substantial protection against an aircraft impact and thus further enhancing the security of the design. The demonstration of key components such as the electromagnetic pumps and the steam generator is part of an ongoing testing program that has already confirmed many of the 4S engineering solutions. This paper describes the current status of design and component tests for the 4S reactor.

Long-lived FP burning based on the actinide recycle metal fuel core

Abstract Feasibility of burning of the major long-lived FPs (I, Pd, Tc, Sn, Se, Zr, Cs) while maintaining fuel breeding capability for the Self-Consistent Nuclear Energy System is evaluated based on the actinide recycle metal fuel core of a fast reactor. It is shown that I, Pd, Tc, Sn, Se, and Zr can be burnt simultaneously by an aid of the isotope separation of Pd-107, Zr-93 and Se-79. Cs, which is difficult to burn with the other FPs, should be utilized as an in-reactor shielding material to confine in the system. The selection of the target FPs to be burnt are also validated by using the Burden Index. The overall assessment based on those results indicates that the developed system has the great potential to achieve the goal of the Self-Consistent Nuclear Energy System.

An Axially and Radially Two-Zoned Large Liquid-Metal Fast Breeder Reactor Core Concept

A new core concept that has advantages over conventional homogeneous cores in neutronics characteristics such as power peaking factor, burnup reactivity loss, and reactivity response to the movement of control rods in earthquakes has been evolved. Two options of the new core concept are feasible. One is the so-called axially heterogeneous core, with the internal blanket placed at the lower part of the core. The other concept is similar to the conventional homogeneous core, but has two different plutonium-enriched zones in the axial as well as in the radial direction, so it is a hybrid type of the conventional homogeneous core and the axially heterogeneous core. The new design concept is described and the way that the core characteristics are improved by the chosen key parameters is shown.

Neutronic feasibility of an LMFBR super long-life core (SLLC)

Abstract The LMFBR Super Long-Life Core (SLLC) concept has evolved over the last few years as one of the targets of innovative approaches for future FBR cost reduction. An idea for SLLC has been developed wherein the core lifetime is extended up to the plant life of about 30 years by applying the radially and axially multi-zoned core concept (the improved homogeneous core concept). The main purpose of the present study is placed on the evaluation of neutronic feasibility of the 1000 MWe class SLLC concept. The core size of the present SLLC, which is approximately 3 to 4 times as large as those of the current 1000 MWe core design, was determined by the limit of the maximum fast neutron fluence level, which was tentatively assumed to be 5–6 × 10 23 nvt as the target of the future development of advanced cladding materials. Emphasis is placed on the discussion of neutronic performances of cores with oxide fuels rather than metal or carbide fuels. The present study has shown that proper zoning of the different plutonium enrichment fuels at the initial core makes it possible to achieve small enough reactivity loss during 30-year burnup while satisfying mild variation of the subassembly power distributions using a higher fuel volume fraction of about 50%. Effects of important neutronic parameters on the core performances are also discussed.

A concept of the multipurpose liquid metallic-fueled fast reactor system (MPFR)

Against fossil fuels, the nuclear energy is the only alternative energy source in the next century. Such energy source as the future nuclear power plant is expected to meet the following requirements. First, high temperature output for the multiple energy conversion capability as the electricity generation and the production of alternative fuels (hydrogen), which can be used widely in transportation systems. Second, the capability for siting close to the energy consumption area without onsite refueling. Third, the capability for nuclear fuel breeding and incineration of long-lived fission products, and fourth, the harmonization between active and passive safety features. This paper describes the basic concept of the Multipurpose liquid metallic-fueled Fast Reactor system (MPFR), which satisfies all mentioned requirements with introducing the U-Pu-x (x: Mn, Fe, Co) liquid metallic alloys for the fuel. We can obtain such characteristics as high operational temperature of the reactor (between 550 °C and 1200 °C) and elongation of the core operational lifetime by the inherent fission product separation in the liquid fuel by using these alloys. The enhanced self-controllability is achieved by the thermal expansion of liquid fuel; and the re-criticality phenomenon at the core compaction events can be eliminated by discharging of the liquid fuel from the core.

Development of Uranium-Free TRU Metallic Fuel Fast Reactor Core

A TRU-burning fast reactor cycle associated with a uranium-free trans-uranium (TRU) metallic fuel core is one of the solutions for radioactive waste management issue. Use of TRU metallic fuel without uranium makes it possible to maximize the TRU transmutation rate in comparison with uranium and plutonium mixed-oxide fuel because it prevents the fuel itself from producing new plutonium and minor actinides, and furthermore because metallic fuel has much smaller capture-to-fission ratios of TRU than those of mixed-oxide fuel. Also, adoption of metallic fuel enables recycling system to be less challenging, even for uranium-free fuel, because a conventional scheme of fuel recycling by electrorefining and injection casting is applicable.

A metal fuel fast reactor core for the Self-Consistent Nuclear Energy System

Feasibility of transmutation of the major long-lived FPs (I, Pd, Tc, Sn, Se, Zr, Cs) while maintaining fuel breeding capability for the Self-Consistent Nuclear Energy System is evaluated based on the actinide recycle metal fuel core of a fast reactor. It is shown that I, Pd, Tc, Sn, Se, and Zr can be transmuted simultaneously by an aid of the isotope separation of Pd-107, Zr-93, Sn-126 and Se-79. Cs, which is difficult to transmute with the other FPs, is planned to be utilized as an in-reactor shielding material to confine in the system The overall assessment based on those results indicates that the developed system has the great potential toward the Self-Consistent Nuclear Energy System.