Integral nuclear power reactor with natural coolant circulation. Investigation of passive RHR system

Nuclear Engineering and Design

Volumn 165, Issue 1-2, 1996, Pages 259-264

  Samoilov, O B ^a   Kuul, V S ^a   Malamud, V A ^a   Tarasov, G I ^a  

^a AO Afrikantov OKB Mechanical Engineering Company   (Russian Federation)

Author keywords

Natural coolant cirulation; Passive RHR

Indexed keywords

ACCIDENT PREVENTION; COOLANTS; COOLING SYSTEMS; MATHEMATICAL MODELS; NUCLEAR POWER PLANTS; PRESSURE VESSELS; REACTOR CORES; SECURITY SYSTEMS; STEAM GENERATORS; TEST FACILITIES;

INTEGRAL NUCLEAR POWER REACTOR; NATURAL COOLANT CIRCULATION; PASSIVE SAFETY SYSTEMS; PRESSURIZER; PRIMARY CIRCUITS; SELF ACTIVATED CONTROL DEVICES; STEAM CONDENSING CHANNELS;

PRESSURIZED WATER REACTORS;

EID: 0030564615     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/0029-5493(96)01188-0     Document Type: Article

References (2)

1. O.B. Samoilov, V.A. Malamud et al., Small Power Nuclear Co-Generation Plant With Integral PWR. Presentation to Int. Conf. on Design and Safety of Adv. Nuclear Power Plants, Tokyo, Japan, October 25-29, 1992.
2. O.B. Samoilov, V.S. Kuul and G.I. Tarasov, Passive steam-condensing channel for emergency heat removal in integral reactor. Presentation to Int. Conf. on New Trends in Nuclear System Thermohydraulics, Pisa, Italy, May 30th -June 2nd, 1994.