Perspectives on reactor safety

Technical Report · Mon Feb 28 23:00:00 EST 1994

DOI:https://doi.org/10.2172/10139184· OSTI ID:10139184

Haskin, F E ^[1]; Camp, A L ^[2]

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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)

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) historical perspective; (2) accident sequences; (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). Div. of Safety Issue Resolution; New Mexico Univ., Albuquerque, NM (United States). Dept. of Chemical and Nuclear Engineering; Sandia National Labs., Albuquerque, NM (United States)
• Sponsoring Organization: Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: AC04-94AL85000
• OSTI ID: 10139184
• Report Number(s): NUREG/CR--6042; SAND--93-0971; ON: TI94009375; BR: GB0103012
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210700
22 GENERAL STUDIES OF NUCLEAR REACTORS
220200
220900
COMPONENTS AND ACCESSORIES
CONTAINMENT
EMERGENCY PLANS
ENVIRONMENTAL EFFECTS
HISTORICAL ASPECTS
PERSONNEL
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTOR VESSELS
REGULATION AND LICENSING
SOURCE TERMS
TRAINING
US NRC