0000001893 00000 n x�|w(TQ�5� ����;8��ȋ��&;5Ց��������0�^��D#^����6�yБ�鄝ϗ'�l+D�F o�>-�R2-%�y{}6��Ž�Z��~ZL���R {> In 2015, the US Department of Energy (DOE) opted to build on the AHR NUREG-1537 ISG experience by performing a gap analysis of the guidance that would be used to license a non-power MSR. The gaseous fission products will be collected and held for decay in an off-gas system. Fast Reactor (SAMOFAR) project. Standard review plan (SRP) guidance for large light water reactors (LWRs) is available in NUREG-0800, Molten Salt Thermophysical Properties Database Development: 2019 Update, 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS. 0000003263 00000 n \#��K6��t��#��,�a�P��.�۸��L�Ԥ�R�������}��s/�����A�F��an���v�j��@�I|4��7�QG*3��i��考�Z��b���s"��� ��I�� ��O9�����a�8+� j�ۇC`�O���(x��D��Gw�ǡ�È3;���k'pI����h��HՌ�b�(*�Ge�A2��.݁�Cs�5:��� ���3���o��8U�)�C� L2�� 0000005018 00000 n In order to design large production facilities, accurate physical and thermodynamic properties of molten salts must be known. Development of non-power molten salt reactors (MSRs) are under consideration to further establish an MSR experience base, support the requirements of Title 10 of the Code of Federal Regulations (10 CFR) Section 50.43(e), and provide any additional analyses needed for development of a full-scale MSR. trailer This report also provides a high-level, parametric evaluation of LSHT loop performance to allow general intercomparisons between heat-transport fluid options as well as provide an overview of the properties and requirements for a representative loop. 0000010065 00000 n 0000012898 00000 n endstream endobj 112 0 obj<> endobj 113 0 obj<> endobj 114 0 obj<> endobj 115 0 obj<>/ProcSet[/PDF/Text]/ExtGState<>>> endobj 116 0 obj<> endobj 117 0 obj<> endobj 118 0 obj<> endobj 119 0 obj<> endobj 120 0 obj<> endobj 121 0 obj<> endobj 122 0 obj<> endobj 123 0 obj<> endobj 124 0 obj<> endobj 125 0 obj<>stream h�b```��,\�@ (� Loop operational issues such as start-up procedures and system freeze-up vulnerability are also discussed. %PDF-1.4 %���� h�bbd``b`�$YA��`�� �&�ČAܝ �D��� b�����2H��3L����,F���S� y� ! Despite the availability of some high quality MSR-relevant data-sets, there remains a need for a thermophysical properties experimental program to generate data focused on addressing the design and licensing needs of current MSR concept developers. 0000138564 00000 n The molten salt data were derived from Reference 1. used to link thermochemical models to the multi-physics code, (4) a framework for integrating kinetic phenomena: nucleation, precipitation, mass/heat transport, and corrosion models, and (5) a computational environment to efficiently utilize the data and models within a multi-physics modeling tool. The report also includes a compilation of relevant thermophysical properties of useful heat transport fluoride salts. Fluoride salts are both thermally stable and with proper chemistry control can be relatively chemically inert. Argonne National Lab. The introductions from Parts 1 and 2 of the 2012 NUREG-1537 ISG provide guidance for the application and review of production facilities. h�Ėmo�6�� The treatment and handling of fission products in the non-power MSR fuel salt and the description of this process in the safety analysis report (SAR) must be very precise to avoid the waste treatment facility being construed as a co-located special nuclear material (SNM) fuel cycle facility (see Section 2.3 of this report). 362 0 obj <>stream Much of the information presented here derives from the earlier MSR program. H�tU�n9��+�Hj�K��9�1q�HIq�D�{��4�-{�W�)[������իE'��a�n�8Y�5(X�-��i�(EUU �K��BB��BJY�zC��`����>��8���R��bpc�+a�3�J�Xڶ���On�U��b�+m7�y�ZP�v�iI��o8�� Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants; Light Water Reactor (LWR) Edition. �]Qc����U�KB��~iʷ� �O�|�Ov�}{�&��&�c%�gZ���X�DNQJ,Yy,�TE�����y�����*�.�I/�@��]�ܣ�Zb��+ޠX(����Zp���/P7�����,��K�d:VF��\ύ��zu�K�j�c`&����n��� Part 1, the format and content guide, suggests a uniform format for presenting information in non-power reactor applications that is acceptable to the NRC staff, but conformance with the format and content is not required. 0000001654 00000 n H�dUMo�8��W�(������C���{Pl͌G2$9���_R�3��4-�Ga���q���C�zq�Y��$]f�~��,ċ��٨���C��!̿�=$[�� The report includes an overview of the state-of-the-art in reduction-oxidation chemistry control methodologies employed to minimize corrosion issues. 0000010989 00000 n Subsequent to the release of ORNL/TM-2018/834, NRC staff expressed a desire to continue the regulatory gap analysis that was begun in that report. %PDF-1.4 %���� These reactors, unless owned by the DOE or DOD, will require licensing by the US Nuclear Regulatory Commission (NRC) staff. ���0�fd`b� A��c7� g`x` ߐ�� This activity required defining a format for thermophysical properties that could be produced from salt, To aid in design and licensing of molten salt reactors, a framework integrating the complex interaction of reactor neutronics, thermal hydraulics, and chemistry is being developed within the Department of Energy Advanced Reactor Technology Program’s Molten Salt Reactor (MSR) campaign. 0000009160 00000 n A goal of the Molten Salt Reactor Campaign is to develop a quality-controlled database of these properties that will be available for a multitude of different salt types. 0000000996 00000 n 0000004223 00000 n x�b```f``qc`e`��fa@ ��7e����d��x���z*�?���[��ױ� Chemical and Fuel Technologies Div. �#��?�5�s��B+1��,�ş�2���zN��f��x)�S���s�m A particular advantage of fluoride salts is that the technology for their use is relatively mature as they were extensively studied during the 1940s-1970s as part of the U.S. Atomic Energy Commission's program to develop molten salt reactors (MSRs). The structure of the new MSR thermophysical properties database is outlined and three datasets are reviewed in detail to provide examples of the data and metadata that will be included in the database. Useful risk analyses tools currently in use for developing MSR source term analyses are also summarized, such as those developed for the European Safety Assessment of the Molten Salt, Successful modeling and simulation of molten salt reactors (MSRs) requires quality thermodynamic and thermophysical data for the working fluid. endstream endobj startxref data delivered by Argonne National Laboratory (ANL) and which could be read into a reactor analysis tool. 0000008293 00000 n 0000145796 00000 n Guidance provided in this report is based on MSRs operating with liquid fuel (i.e., fuel dissolved within a molten salt). �gx�����dC՜�v^�+���"�����)�tzB� �En]b����Ku��"�"�u���L�,S_�xX��mZR�h�ͤ*�v���b�����7d�XT2Ӵf�L�1�S�F��5[S���ի-�v$4Su�"7���i@s:_L ����(�� {cB���i �2et4 )�g3�tt@@����`� ��2�B� 10�I�RҀ�S��Y�0CG�aAb1@Z���"� g�d�dZ�x�����C�K���1733D10[0�1220'2M�=��I}Vb����^��\��N�c�g(`vc�`+��p� s>3�3�ъe��HeWz�!�q 0000007370 00000 n ORNL staff, with support from Boston Government Services, LLC, focused on five system-related chapters in NUREG-1537 that were considered most relevant to inform the effort that would be required for a non-power MSR applicant. (ANL), Argonne, IL (United States). 0 Molten salts are being employed throughout the world as heat transfer fluids and phase change materials for concentrated solar power (CSP) production and storage. In the ORNL report, proposed generic adaptations were suggested for the following NUREG-1537 chapters: Chapter 4, “Reactor Description”; Chapter 5, “Reactor Coolant Systems”; Chapter 6, “Engineered Safety Features”; Chapter 9, “Auxiliary Systems”; Chapter 11, “Radiation Protection Program and Waste Management” The inclusion of Chapter 11 in the previous review effort was intended to provide guidance for categorizing the waste-handling process for an MSR operating with homogenous fuel. 0000012196 00000 n Key words: Molten salt storage tank design, molten salt technology, molten salt properties, molten salt costs, solar energy storage, nuclear energy storage. Unfortunately, the application guidelines and SRP do not provide adequate guidance for all advanced non-LWR technologies and applications. This report is submitted in fulfillment of Advanced Reactor Technologies, Molten Salt Reactor Campaign, Salt Chemistry work package AT-19AN04060104, milestone number M4AT-19AN040601043. endstream endobj 340 0 obj <>stream ��5��*��j[�e�P���ʹ�W�af��=�Q�< endstream endobj 337 0 obj <>/Metadata 27 0 R/PageLabels 332 0 R/PageLayout/OneColumn/Pages 334 0 R/PieceInfo<>>>/StructTreeRoot 42 0 R/Type/Catalog>> endobj 338 0 obj <>/Font<>/ProcSet[/PDF/Text]>>/Rotate 0/StructParents 0/Type/Page>> endobj 339 0 obj <>stream The report includes a high-level, parametric evaluation of liquid fluoride salt heat transport loop performance to allow intercomparisons between heat-transport fluid options as well as providing an overview of the properties and requirements for a representative loop. 145 0 obj<>stream 0000001556 00000 n 0000146266 00000 n 1. In 1996, NUREG-1537, Parts 1 and 2, Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors, was published. Based on the analyses summarized in this report, a pathway is recommended for a rigorous and technology-neutral MSR source term analysis in the U.S. 0000006343 00000 n Part 2, the SRP, ensures the quality and uniformity of the staff review of an application. However, NRC staff observed that NUREG-0800 is very cumbersome to apply to non-power reactors “because of the great differences in complexity and hazards between non-power reactors and nuclear power plants.” Therefore, a program to develop performance-based guidance applicable to non-power reactors was initiated. This report provides an overview of the current status of liquid salt heat transport technology. 0000005120 00000 n Under this Advanced Reactor Concepts 2015 (DOE Advanced Reactor Concepts [ARC] 15) award program, the DOE tasked Oak Ridge National Laboratory (ORNL) to evaluate the guidance changes that the NRC may need to consider when licensing an MSR non-power reactor. A compilation of relevant thermophysical properties of useful fluoride salts is also included for salt heat transport systems. The report also provides an overview of the state-of-the-art in reduction-oxidation chemistry control methodologies employed to minimize salt corrosion as well as providing a general discussion of heat transfer loop operational issues such as start-up procedures and freeze-up vulnerability. Salt chemistry control technology, however, remains at too low a level of understanding for widespread industrial usage. Successful modeling and simulation of molten salt reactors (MSRs) requires quality thermodynamic and thermophysical data for the working fluid. 0000004744 00000 n In addition to being able to get fluid properties into the simulation tool, it is also necessary that a process exists for adding new salt data to the salt database. 0 Much of the information presented here derives from the earlier molten salt reactor program and a significant advantage of fluoride salts, as high temperature heat transport media is their consequent relative technological maturity. <<63ECF252119346478505FC4D79F8234A>]>> This report provides a basis for developing an MSR source term model by examining the successful methodology used in the sodium fast reactor (SFR) mechanistic source term work presented by Grabaskas et al., [2016a]. 0000005401 00000 n 0000002041 00000 n 0000011288 00000 n �#^��旇�Ru�I߲ؓ�Pґ�N�6FBi��3J;��dR�1v��%���O�2�K ��j8�N�?�bĖ�l�h�TX�q.ƿ =�-ڳiuo�� ���/?v����T_�r_!��Gl�'�3Ӎ�o�$�iFR�O��U�"�w���~�o_�����3���п����,�jE �V�"���P]���+�Jcv�a�B0!��d�|��f~g���Z������y�)s�^d��N�H���X�ƃ��dN�(�s�S�Q�ˁ&%���m%�3�R�ɂ[��(�#��x�vO�p�Iq8�%Rbz��.
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