Advanced liquid metal reactor

BERGLUNG, R.C., TIPPETS, F.E., "PRISM, the Plant Design Concept for the U.S. Advanced Liquid Metal Reactor Program", (Conf., Chicago, 1989). [Pg.154]

Uniaxial (tension and compression) and equibiaxial tests of rubber specimens have been performed at ENEL for both a rather hard rubber compound used in the U.S. Advanced Liquid Metal Reactor (ALMR) Project (shear modulus G = 1.4 MPa) and new medium hardness (G = 0.8 MPa) and soft (G = 0.4 MPa) compounds. Tests concerning tiie ALMR rubber have been carried out in the framework of a co-operation with GE Nuclear Energy. [Pg.139]

The main objectives of the R D program and a tentative schedule with 5 progressing stages for the development of KALIMER(Korea Advanced Liquid MEtal Reactor) are given and the current LMR experiences are briefly described. [Pg.185]

The construction of a prototype or demonstration type KALIMER(Korea Advanced Liquid MEtal Reactor) is essential to accomplish the goal of the LMR development. For the construction time, the year 2011 is suggested as established in the LMR long-term development plan. [Pg.188]

For the AFC to be most effective and reduce the inventory of minor actinides at a reasonable rate, dedicated devices that produce a hard or fast neutron spectrum will be required. Such devices include the advanced liquid metal reactors (ALMRs), a fast reactor configured to operate as an actinide incinerator rather than breeder and accelerator-driven systems (ADSs). Fast reactor technology discussed earlier in this chapter is relatively mature whereas the development of ADS is in its infancy. Accelerator-based waste transmutation programs are ongoing in France, Japan, USA, and CERN. [Pg.2830]

Currently there are four modular small or medium-sized, liquid metal reactors. The Advanced Liquid Metal Reactor (ALMR) former (PRISM), the Modular Double Pool Reactor, the 4S (Super, Safe, Small and Simple) and the BMN-170. [Pg.113]

The "Advanced Liquid Metal Reactor (ALMR)" by General Electric et al. (former PRISM... [Pg.28]

The technology base for the LFR is primarily derived from the Pb-Bi liquid alloy-cooled reactors employed by the Russian Alpha class submarines. Technologies developed from the integral fast reactor metal alloy fuel recycle and refabrication development, and from the advanced liquid metal reactor (ALMR) passive safety and modular design approach, may also be applicable to the LFR. The ferritic stainless steel and metal alloy fuel developed for sodium fast reactors may also be adaptable to the LFR for those concepts with reactor outlet temperatures in the range of BSO C. [Pg.311]

KALIMER-150 (Republic of Korea) Korean Advanced Liquid MEtal Reactor... [Pg.5]

The ADVANCED LIQUID METAL REACTOR (ALMR) plant has three redundant... [Pg.209]

Berglund, J.R.C., et al.. Performance and Safety Design of the Advanced Liquid Metal Reactors, Proc. of the Intemat. Conference on Fast Reactors and Related Fuel Cycles, Kyoto, Japan, 1991, Vol. 2. [Pg.223]

Advanced liquid metal reactor design description... [Pg.484]

Gluekler, E.L., Quinn, J.E., Advanced Liquid Metal Reactor (LMR) R D Program - Focus on Innovation. Ibid... [Pg.532]

The LMR design technology development project was approved as a national long-term R D programme in 1992 by the Korea Atomic Energy Commission (KAEC), which decided to develop and construct a liquid metal cooled reactor (LMR). Based upon the KAEC decision, the Korea Atomic Energy Research Institute (KAERI) has been developing KALIMER (Korea Advanced Liquid Metal Reactor) [XX-1, XX-2]. [Pg.553]

Based on the success of the previous DOE sponsored advanced liquid metal reactor (ALMR) programme, the General Electric has continued to develop and assess the technical viability... [Pg.568]

ALMR Advanced Liquid Metal Reactor LCO limiting condition of operation... [Pg.8]

Examine the use of alternative coolants and concepts such as the Modular High Temperature Gas-Cooled Reactor (MHTGR) and the Advanced Liquid Metal Reactor (ALMR). There was not time in the preliminary design work to study in detail the possibility of use of other coolants. Alternative coolants should be evaluated considering both core neutronics and thermal hydraulics. [Pg.23]

The Pu-2H wt% Zr alloy is being proposed for the advanced liquid metal reactor plutoniumburning power reactor. It appears attractive for fast reactor concepts, but considerably more dilution of the plutonium would be required in a thermal reactor. The melting temperature of this alloy system is roughly proportional to the atomic percentage of zirconium, which melts at 2130 K (plutonium melts at 915 K). Fabrication could be achieved by melting and casting the alloy. [Pg.61]

The break of a pipe reduces the core flow, which results in power-to-flow mismatch for some seconds after the pipe break occurred. However, the power is stabilized, even though the automatic reactor scram is not activated. The GEM play an important role in providing the dominant reactivity feedback in case of an important core flow reduction resulting in the decrease of the GEM level below the top of the active core. The results of the primary coolant pipe break event analyses performed for the Korea Advanced Liquid Metal Reactor (KALIMER), which adopts several advanced design features, prove both a coolant subcooling margin of more than 400 K, and a stable system response. [Pg.12]

ANALYSIS OF PRIMARY PIPE BREAK FOR THE KOREAN ADVANCED LIQUID METAL REACTOR (KALIMER)... [Pg.105]

The inherent safety characteristic against postulated events is the most remarkable superiority of a liquid metal cooled reactor (LMR) to other type of reactors. One of the major threats to the safety of LMR is a loss of flow event accompanied a failure of reactor shutdown systems. This situation is usually referred to as an unprotected loss of flow (ULOF). The inherent safety of the Korean Advanced Liquid Metal Reactor (KALIMER) during the ULOF [I] has been assessed for the situation of all pump trips followed by coastdown. It was assumed that the decay heat is removed by four intermediate heat exchangers (IHXs) and the safety grade system of passive safety decay heat removal system (PSDRS). The results showed that the power was stabilized by the reactivity feedback of the system even though the effect of the gas expansion module (GEM) was not taken into account. [Pg.105]

KALIMER Korean Advanced Liquid Metal Reactor... [Pg.146]

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