Published 1993 | Version v1
Journal article

Plant protection system optimization studies to mitigate consequences of large breaks in the advanced neutron source reactor

  • 1. Oak Ridge Institute for Science and Education, TN (United States)
  • 2. Oak Ridge National Lab., TN (United States)

Description

This paper documents some of the optimization studies performed to maximize the performance of the engineered safety features and scram systems to mitigate the consequences of large breaks in the primary cooling system of the advanced neutron source (ANS) reactor. The ANS is a new basic and applied research facility based on a powerful steady-state research reactor that provides beams of neutrons for measurements and experiments in the field of material science and engineering, biology, chemistry, material analysis, and nuclear science. To achieve the high neutron fluxes for these state-of-the-art experiments, the ANS design has a very high power density core (330 MWfission with an active volume of 67.6 ell) surrounded by a large heavy-water reflector, where most neutrons are moderated. This design maximizes the number of neutrons available for experiments but results in a low heat capacity core that creates unique challenges to the design of the plant protection system

Additional details

Publishing Information

Journal Title
Transactions of the American Nuclear Society
Journal Volume
69
Journal Page Range
p. 267-269.
ISSN
0003-018X
CODEN
TANSAO

Conference

Title
American Nuclear Society (ANS) winter meeting.
Dates
14-18 Nov 1993.
Place
San Francisco, CA (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
26026195
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
DESIGN; ENGINEERED SAFETY SYSTEMS; LOSS OF COOLANT; NEUTRON FLUX; POWER DENSITY; REACTOR PROTECTION SYSTEMS; REACTOR SAFETY; RESEARCH REACTORS; SAFETY ANALYSIS; SCRAM
Descriptors DEC
ACCIDENTS; RADIATION FLUX; REACTOR ACCIDENTS; REACTOR SHUTDOWN; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; SHUTDOWN

Optional Information

Secondary number(s)
CONF-931160--.