skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Discussion of Key Technical Issues Re: Components of the Safety Case.


Abstract not provided.

Publication Date:
Research Org.:
Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
Sponsoring Org.:
USDOE National Nuclear Security Administration (NNSA)
OSTI Identifier:
Report Number(s):
DOE Contract Number:
Resource Type:
Resource Relation:
Conference: Proposed for presentation at the 7th US/German Workshop on Salt Repository Research, Design, and Operation held September 7-9, 2016 in Washington, DC.
Country of Publication:
United States

Citation Formats

Sevougian, S. David. Discussion of Key Technical Issues Re: Components of the Safety Case.. United States: N. p., 2016. Web.
Sevougian, S. David. Discussion of Key Technical Issues Re: Components of the Safety Case.. United States.
Sevougian, S. David. Mon . "Discussion of Key Technical Issues Re: Components of the Safety Case.". United States. doi:.
title = {Discussion of Key Technical Issues Re: Components of the Safety Case.},
author = {Sevougian, S. David},
abstractNote = {Abstract not provided.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Mon Aug 01 00:00:00 EDT 2016},
month = {Mon Aug 01 00:00:00 EDT 2016}

Other availability
Please see Document Availability for additional information on obtaining the full-text document. Library patrons may search WorldCat to identify libraries that hold this conference proceeding.

Save / Share:
  • Bringing a Nuclear Power Generating Station under the control of an expert system will require an extensive program of coordinated research, development, prototype testing, and regulatory review. Conversion of nuclear energy to electrical energy carries with it a myriad of unique and complicated issues. Some will be purely technical in nature. Other less technical, and more esoteric issues will also impose constraints on the programmer and on the utility. This paper presents and discusses the key issues that relate to the viability of expert systems in the nuclear power arena.
  • Title 4 of the Clean Air Act Amendments of 1990 (CAAA) created a new regulatory instrument that electric power producers (utilities and others) will be required to possess and expand in order to emit sulfur dioxide (SO{sub 2}) into the atmosphere. The emission allowance system created by the CAAA will be grafted onto an already complex system of state and federal electric utility regulation. How public utility commissions (PUCs) and the Federal Energy Regulatory Commission (FERC) regulate these allowances will greatly affect the decisions that electric utilities under their jurisdiction make to comply with the CAAA and, therefore, the costmore » of compliance to ratepayers. 2 figs., 9 tabs.« less
  • This paper presents a review of research on key US reactor safety issues in liquid-metal-cooled reactors (LMRs) over the past decade. The discussion is structured into two time domains: 1) the FFTF/CRBRP era, which featured a mixed oxide fuel system, and 2) the present era which emphasizes passive safety and a renewed emphasis on metal fuel. Issues in the FFTF and CRBRP era include local fault tolerance, core energetics potential (in response to unprotected transient overpower, loss of flow, or loss of heat sink events), and containment considerations. Issues of current interest focus much more heavily on reactivity feedbacks capablemore » of preventing the core from entering into a state of disruption /endash/ even for very low probability postulated events. Overall, the RandD over the past decade has provided generally favorable answers to safety concerns expressed in the early days of LMR design. Furthermore, the more recent programmatic directions /endash/ which emphasize passive safety /endash/ provide even stronger assurances that LMRs can be built which are exceptionally robust. 75 refs., 4 figs., 2 tabs.« less
  • The development of the common French-German safety approach started in 1992 after a preparatory phase of about 2 years. It was accomplished on three working levels: the technical safety organizations GRS (Gesellschaft fuer Anlagen- und Reaktorsicherheit) and IPSN (institute de Protection et de Surete Nucleaire) developed the technical basis, advisory groups GPR (Groupe Permanent charge des Reacteurs Nucleaires) and RSK (Reaktorsicherheitskommission) developed common recommendations, and the authorities BMU (Bundesministerium fuer Naturschutz, Umwelt und Reaktorsicherheit) and DSIN (Direction de la Surete des Installations Nucleaires) issued the common safety approach. The general common safety approach issued in May 1993 contains safety objectives,more » general principles and already some technical principles. Important objectives are to reduce the annual probability of core melt, to exclude large early releases and to mitigate low pressure core melt sequences so that the associated maximum conceivable release would necessitate only very limited protective measures in area and in time. Based on this general safety approach, more detailed recommendations have been developed in 1994. A selection of the detailed recommendations is presented in the full paper. These recommendations are applicable to the EPR project for which the basic design is now underway.« less