Investigation of bleed-and-feed procedures for mitigating the consequences of a total loss-of-feedwater transient: IIST experiments

Book · Tue Dec 31 00:00:00 EST 1996

OSTI ID:445422

Lee, C H; Liu, T J; Chang, C Y; Hong, W T; Chan, Y K; Hwang, I M; Chang, C J ^[1]

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1. Inst. of Nuclear Energy Research, Lung-Tan (Taiwan, Province of China)

A reduced-height and reduced-pressure (RHRP) INER (Institute of Nuclear Energy Research) Integral System Test (IIST) facility has been built for simulating the thermal hydraulics (T/H) behavior of Westinghouse three-loop pressurized water reactor (PWR). Experiments on loss of all feedwater (LOFW) with no operator action and with reactor coolant system (RCS) bleed and feed were conducted at the IIST facility. The experimental results not only explore the key (T/H) phenomena during LOFW transients but also show the validation of RCS bleed-and-feed procedures for mitigating the consequence of LOFW transient.

• OSTI ID: 445422
• Report Number(s): CONF-961105-; ISBN 0-7918-1544-7; TRN: 97:005128
• Resource Relation: Conference: 1996 international mechanical engineering congress and exhibition, Atlanta, GA (United States), 17-22 Nov 1996; Other Information: PBD: 1996; Related Information: Is Part Of Thermal science of advanced steam generators/heat exchangers. NE-Volume 19; Hassan, Y.A. [ed.] [Texas A and M Univ., College Station, TX (United States)]; Beus, S. [ed.] [Bettis Atomic Power Labs., West Mifflin, PA (United States)]; PB: 92 p.
• Country of Publication: United States
• Language: English

Related Subjects

22 NUCLEAR REACTOR TECHNOLOGY
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS
PWR TYPE REACTORS
LOSS OF COOLANT
REACTOR SAFETY EXPERIMENTS
TEST FACILITIES
MITIGATION
EMERGENCY PLANS
EXPERIMENTAL DATA