Published December 1984
| Version v1
Journal article
Study on the reactivity accident analysis of CANDU-type nuclear power reactor
Description
The reactivity accident analysis of CANDU-type nuclear reactor has been performed for the case of postulated loss of coolant accident. The analysis has been carried out by using the computer code KIND which has solved the nuclear reactor kinetics equations by means of alternating direction explicit method. The analysis has been performed space-time neutronic behavior of the reactor. The relative average neutron power has been increased during response time with 2.753 times of steady state and decreased during subsequent insertion of shutdown system with 0.865 times of steady state. It has been confirmed that the CANDU-PHW reactor has shutdown capability of shutoff rods system in case of half core loss of coolant accident. (Author)
Additional details
Publishing Information
- Journal Title
- Chungnam J. Sci., Chungnam Natl. Univ.
- Journal Volume
- 11
- Journal Issue
- 2
- Series
- Chungnam J. Sci., Chungnam Natl. Univ.
- Journal Page Range
- 67-74
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 16054759
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- CANDU TYPE REACTORS; K CODES; LOSS OF COOLANT; NUCLEAR POWER PLANTS; REACTIVITY; REACTOR ACCIDENTS; REACTOR SHUTDOWN
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; HEAVY WATER MODERATED REACTORS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; SHUTDOWN; THERMAL POWER PLANTS; THERMAL REACTORS