Water cooled SMRs

Of the twenty-six concepts and designs addressed, 13 (50%) are water cooled SMRs, 6 (23%) are gas cooled SMRs-high temperature gas cooled reactors (HTGRs), 6 are sodium or lead-bismuth cooled fast reactors, and 1 is a non-conventional very high temperature reactor concept, a liquid salt cooled reactor with HTGR type prismatic fuel. [Pg.14]

For all innovative SMRs addressed in this report. Table 2 provides a summary of the user-related features, the targeted deployment dates, the achieved design and regulatory status and its progress since previous IAEA publications, identifies fuel cycle options and specifies the recommended sources of additional information. [Pg.14]

A short review of these data, structured according to the reactor types, is provided in Sections 3.1.1-3.1.4 below. [Pg.14]

Company / Institution KAERI, MOST International consortium (10 countries) lead by Westinghouse (USA) [Pg.15]

Reactor style Integral type Integral type [Pg.15]

As it can be seen from both Fig. 1 and Table 1, water cooled SMRs are the most suitable candidates for a near-term deployment. The high temperature gas cooled reactors with thermal neutron spectrum follow them closely. Small PWR designs from Russia are based on the experience of the marine reactors and are said to be deployable within a very short term, once the financing for a necessary limited amount of the Research, Design Demonstration (RD D) becomes available. [Pg.4]

Some passive decay heat removal systems, such as a water tank surrounding the reactor vessel of a lead-bismuth cooled SVBR-75/100, could be effective for many heavy metal cooled SMRs. They are also quite common to many innovative water cooled SMRs. To abandon the off-site emergency planning it may be important to develop passive heat removal systems that are effective over the whole run of a design basis accident or even an anticipated transient without scram. This may be a task important for many SMR designs representing several reactor lines. [Pg.23]

All designers of the innovative water cooled SMRs would attempt to reduce or eliminate the off-site emergency planning requirements in licensing ... [Pg.32]

DESIGN AND SAFETY OF IRIS, AN INTEGRAL WATER COOLED SMR FOR NEAR TERM DEPLOYMENT... [Pg.51]

A preferable choice for the electric output, as observed in 9 out of 13 water cooled SMR concepts, is around 300 MW (from 250 to 350 MW) excluding prototypes. The SCOR with its 630 MW(e) provides a notable exception towards higher outputs. The lowest output of 70... [Pg.29]

Of the thirteen concepts and designs of water cooled SMRs, five (SMART, CAREM-25, VBER-300, VK-300, and AHWR) are at the detailed design stage four (IRIS, MARS, CCR and RUTA-70) are at the basic (preliminary) design stage others are at the conceptual or early conceptual (KAMADO) design stages. [Pg.29]

Once-through fuel cycle with low-enrichment uranium dioxide fuel is foreseen as basic for most of the water cooled SMRs. The exceptions are (i) the RMWR, which is a breeder reactor designed to operate in a closed U-Pu fuel cycle and (ii) the AHWR with the once-through Pu-Th- U fuel cycle specified as basic. [Pg.30]

This report does not address evolutionary SMRs. The descriptions of many of such designs, which are mostly water cooled reactors, can be found in [19, 20]. One could argue that some water cooled SMRs included in this report appear more like the evolutionary designs with innovative features but, as mentioned in Section 1.3, the decision to include them was made by their designers who also provided the justifications of why they rate their designs as innovative. [Pg.34]

Pre-fabrication of components and modular approach to plant construction are foreseen for most of the water cooled SMRs the VBER-300 provides for full factory fabrication. [Pg.36]

The following technical features to minimize the production of wastes are commonly mentioned by the designers of innovative water cooled SMR ... [Pg.39]

The designers of all innovative water cooled SMRs considered in this report pursue an enhanced prevention or elimination of abnormal operation and failures (Level 1 in Table 4). The design features to achieve such elimination or prevention are specified as the following ... [Pg.42]

Regarding the control of accidents within the design basis (Level 3 in Table 4), all water cooled SMRs rely on certain inherent safety features (such as the reactor vessel penetrations located in the upper, steam part of the reactor pressure vessel to ensure that the leakage rate is low and the core is not uncovered in loss of coolant accidents ) and incorporate various combinations of passive and active systems. Most of the designs target an increased reliance on passive systems, as benefiting from smaller reactor size. In different water cooled SMRs, passive systems shoulder the functions of back up or main shutdown systems, emergency core... [Pg.42]

Several designers of water cooled SMRs (e.g., MARS, SCOR, CCR) examine passive in-vessel retention of corium (Level 4 in Table 4). [Pg.43]

Last but not least, the designers of many innovative water cooled SMRs target the reduced or eliminated ofif-site emergency planning (Level 5 in Table 4), pointing to very low... [Pg.43]

Most of the design descriptions of water cooled SMRs specify low enrichment uranium and once-through fuel cycle as basic options. Therefore, the features contributing to proliferation resistance of such SMRs are essentially similar to that of presently operated PWRs and BWRs. They include low enrichment of fresh fuel, low residual... [Pg.47]

Other features specified by the designers of individual water cooled SMRs are the following ... [Pg.48]

Most of the innovative water cooled SMRs addressed in this report incorporate the following technical features to support physical protection of the plant ... [Pg.49]

For convenience. Tables ni l through III.9 follow the pattern used in the annexes to this report, i.e., water cooled SMRs appear first, followed by gas cooled, sodium cooled, lead-bismuth cooled and non-conventional SMRs. The order of certain designs within each of the abovementioned groups also follows the sequence used in the annexes, with the corresponding annex number being indicated against each SMR name. [Pg.51]

Several of the innovative water cooled SMRs incorporate integral designs of primary circuits. The corresponding further R D will include validation and testing of the performance of such integral circuits and their main components. Specifically, the need of further R D on natural circulation is specified for many innovative water cooled SMRs. [Pg.52]

Regarding control and protection systems, several innovative water cooled SMRs target the use of control rod drives (CRDs) of the advanced designs. In this connection, the upper entry CRDs could be mentioned for BWRs, and the in-vessel CRDs for PWRs. [Pg.53]

The majority of inputs for all SMRs correspond to the ongoing or planned R D for a variety of different passive systems. Specifically, the in-vessel retention of corium by passive means is indicated as a design objective for three water cooled SMRs. [Pg.53]

Provisions for fiill-scope fuel cycle service agreements or fuel leasing Water cooled SMRs IRIS (Annex H) CAREM (Annex III) VBER-300 (Annex VII) RMWR (Annex X) RUTA-70 (Annex XII) Gas cooled SMRs GT-MHR (Annex XV) ACACIA (Annex XIX) Liquid metal cooled SMRs BMN-170 (Annex XXI) RBEC-M (Annex XXIU) 9... [Pg.56]

Option of a turnkey contract for a NPP Water cooled SMRs SMART (Atmex I) CAREM (Annex III) Gas cooled SMRs GT-MHR (Annex XV) 3... [Pg.57]

Increased local participation in NPP construction Water cooled SMRs MARS (Annex IV) VBER-300 (Annex VII) AHWR (Annex XI) 3... [Pg.57]

No information provided Water cooled SMRs SCOR (Annex V) KAMADO (Annex XIII) Gas cooled SMRs FAPIG-HTGR (Annex XVm) Liquid metal cooled SMRs PEACER (Annex XXIV) MS-LBCR (Annex XXV) Non-conventional SMRs AHTR (Annex XXVI) 6... [Pg.57]

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