Perspectives on reactor safety. Revision 1

Technical Report · Fri Oct 31 23:00:00 EST 1997

DOI:https://doi.org/10.2172/569128· OSTI ID:569128

Haskin, F E ^[1]; Camp, A L ^[2]; Hodge, S A ^[3]

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1. New Mexico Univ., Albuquerque, NM (United States). Dept. of Chemical and Nuclear Engineering
2. Sandia National Labs., Albuquerque, NM (United States)
3. Oak Ridge National Lab., TN (United States). Engineering Technology Div.

The US Nuclear Regulatory Commission (NRC) maintains a technical training center at Chattanooga, Tennessee to provide appropriate training to both new and experienced NRC employees. This document describes a one-week course in reactor safety concepts. The course consists of five modules: (1) the development of safety concepts; (2) severe accident perspectives; (3) accident progression in the reactor vessel; (4) containment characteristics and design bases; and (5) source terms and offsite consequences. The course text is accompanied by slides and videos during the actual presentation of the course.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (United States). Technical Training Div.; New Mexico Univ., Albuquerque, NM (United States). Dept. of Chemical and Nuclear Engineering; Sandia National Labs., Albuquerque, NM (United States); Oak Ridge National Lab., TN (United States)
• Sponsoring Organization: Nuclear Regulatory Commission, Washington, DC (United States)
• OSTI ID: 569128
• Report Number(s): NUREG/CR--6042-Rev.1; SAND--93-0971-Rev.1; ON: TI98003254
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
CHERNOBYLSK-4 REACTOR
CONTAINMENT
EDUCATIONAL TOOLS
EMERGENCY PLANS
NUCLEAR POWER PLANTS
PERSONNEL
REACTOR ACCIDENTS
REACTOR SAFETY
REGULATIONS
RISK ASSESSMENT
SOURCE TERMS
THREE MILE ISLAND-2 REACTOR
TRAINING
US NRC