Use of risk-informed methodology in nuclear criticality safety. Panel Discussion
Creators
- 1. U.S. Nuclear Regulatory Commission, 11555 Rockville Pike, Rockville, MD 20852-2738 (United States)
- 2. BWX Technologies, P.O. Box 785, Lynchburg, VA 24505 (United States)
- 3. Defense Nuclear Facilities Safety Board, Suite 700, 625 Indiana Avenue, NW, Washington, DC 20004 (United States)
- 4. Constellation Nuclear Services, Inc., 2200 Defense Highway, Suite 405, Crofton, MD 21114-2402 (United States)
- 5. Los Alamos National Laboratory, P.O. Box 1663, Los Alamos, NM 87545 (United States)
- 6. Framatome Technologies, 3315 Old Forest Road, Lynchburg, VA 24506 (United States)
Description
Full text of publication follows: The nuclear industry and regulators are moving to a 'risk-informed' methodology in the evaluation of nuclear criticality safety (e.g., the Disposal Criticality Topical Report YMP-004Q and the standard review plans for Part 70 licensees). Moving to a risk-informed methodology has two components: The first is a likelihood of occurrence; the other is the consequence associated with the proposed event. This panel discussion will focus on what it means to be risk-informed and how the risk-informed nuclear criticality safety methodology has been, is being, or will be implemented within nuclear facilities and systems (e.g., fabrication and enrichment facilities, storage and transportation casks, and disposal systems). The panel will represent domestic and international regulatory agencies, nuclear facilities, and other interested organizations. (authors)
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 84
- Journal Page Range
- p. 275
- ISSN
- 0003-018X
- CODEN
- TANSAO
Conference
- Title
- American Nuclear Society 2001 Annual Meeting
- Dates
- 17-21 Jun 2001
- Place
- Milwaukee, WI (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 42070336
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CRITICALITY; FUEL FABRICATION PLANTS; ISOTOPE SEPARATION PLANTS; NUCLEAR INDUSTRY; RISK ASSESSMENT; SAFETY ANALYSIS; SPENT FUEL CASKS; SPENT FUEL STORAGE; WASTE TRANSPORTATION
- Descriptors DEC
- CASKS; CONTAINERS; INDUSTRIAL PLANTS; INDUSTRY; MANAGEMENT; NUCLEAR FACILITIES; STORAGE; WASTE MANAGEMENT