Document: NRC Regulatory Guide
Document ID: 9c99a4b7-8619-41f0-b716-262bfdb03941
Document Type: regulatory_guide
Title: Developing Principal Design Criteria for Non-Light Water Reactors + HISTORY - HISTORY 02/2017 – DG-1330 , Proposed Revision 0
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1630/ML16301A307.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.232
CFR Part: 
CFR Title: 

Content:
ugh their Web site: WWW.IAEA.Org/ or by writing the International Atomic Energy Agency P.O. Box 100 Wagramer Strasse 5, A-1400 Vienna, Austria. Telephone (+431) 2600-0, Fax (+431) 2600-7, or E-Mail at Official.Mail@IAEA.Org. 9 Copies of Annals of Nuclear Energy Articles may be obtained through the Science Direct Web site: WWW.ScienceDirect.com. DG-1330, Page 2 34. DOE, Idaho National Laboratories (INL), “Mechanistic Source Terms White Paper,” INL/EXT- 10-17997, Rev.0, July 2010, (ADAMS Accession No. ML102040260). 35. DOE. INL, “Modular HTGR Safety Basis and Approach,” Idaho National Laboratory, INL/EXT- 11-22708, Rev.0, August 2011, (ADAMS Accession No. ML11251A169). Appendix A to DG-1330, Page A-1 APPENDIX A ADVANCED REACTOR DESIGN CRITERIA The table below contains the advanced reactor design criteria (ARDC). These criteria are generally applicable to six different types of non-light-water reactor (LWR) technologies (i.e., sodium- cooled fast reactors (SFRs), lead-cooled fast reactors, gas-cooled fast reactors, modular high-temperature gas-cooled reactors (mHTGRs), fluoride high-temperature reactors, and molten salt reactors). Applicants/designers may use the ARDC in this appendix to develop all or part of the principal design criteria (PDC) and may choose among the ARDC, SFR-DC (Appendix B), or mHTGR-DC (Appendix C) to develop each PDC. Applicants/designers may also develop entirely new PDC as needed to address unique design features in their respective designs. To develop these ARDC, the staff of the U.S. Nuclear Regulatory Commission (NRC) reviewed each general design criterion (GDC) in Appendix A, “General Design Criteria for Nuclear Power Plants,” to Title 10 of the Code of Federal Regulations (10 CFR) Part 50, “Domestic Licensing of Production and Utilization Facilities,” to determine its applicability to non-LWR designs. The NRC staff then determined what if any adaptation was appropriate for non-LWRs. The results are included in column 2 of