Experience with the AECL digital console
Creators
- 1. Pennsylvania State Univ., University Park (United States)
Description
At the Pennsylvania State University (Penn State), it is believed that nuclear engineering students should have the opportunity to operate a nuclear reactor, perform experiments with reactor and radiation instrumentation, and perform a series of reactor physics experiments. These activities are done at the Penn State Breazeale Reactor (PSBR), a General Atomic Mark III TRIGA reactor. The PSBR, which is part of the Penn State Radiation Science and Engineering Center, is the longest operating university reactor in the US. Through periodic upgrades over its 34-yr lifetime, the facility has enabled the nuclear engineering department to familiarize students with the current instrumentation technology that they would expect to find in industry. The present reactor instrumentation and control system is >25 yr old and is no longer representative of current reactor instrumentation and control technology. The new reactor console was designed to provide the PSBR with safe and reliable operation in four different modes: manual, automatic, square wave, and pulse. It utilizes a reliable hardwired analog system for safety-related functions. All nonsafety-related functions are implemented with computer technology
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 64
- Series
- Trans. Am. Nucl. Soc.
- Journal Page Range
- 254-255
- ISSN
- 0003-018X
- CODEN
- TANSA
Conference
- Title
- 1991 Winter meeting of the American Nuclear Society (ANS) session on fundamentals of fusion reactor thermal hydraulics.
- Dates
- 10-15 Nov 1991.
- Place
- San Francisco, CA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23079343
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ATOMIC ENERGY OF CANADA LTD; CANDU TYPE REACTORS; CONSOLES; DESIGN; DIGITAL SYSTEMS; MAN-MACHINE SYSTEMS; PSTR REACTOR; QUALITY ASSURANCE; REACTOR CONTROL SYSTEMS; REACTOR INSTRUMENTATION; REACTOR KINETICS; REACTOR MONITORING SYSTEMS; REACTOR OPERATION; REACTOR OPERATORS; REACTOR PHYSICS; REACTOR PROTECTION SYSTEMS; REACTOR SAFETY; RELIABILITY; SERVICE LIFE; SPECIFICATIONS; US NRC
- Descriptors DEC
- CANADIAN ORGANIZATIONS; CONTROL SYSTEMS; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; HEAVY WATER MODERATED REACTORS; HOMOGENEOUS REACTORS; HYDRIDE MODERATED REACTORS; KINETICS; LIFETIME; NATIONAL ORGANIZATIONS; OPERATION; PERSONNEL; POOL TYPE REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SAFETY; SOLID HOMOGENEOUS REACTORS; THERMAL REACTORS; TRAINING REACTORS; TRIGA TYPE REACTORS; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-911107--.