Online failed fuel identification using delayed neutron detector signals in pool type reactors
- 1. Power Plant and Control Division, Indira Gandhi Centre for Atomic Research, Kalpakkam (India)
Description
In todays world, nuclear reactors are at the forefront of modern day innovation and reactor designs are increasingly incorporating cutting edge technology. It is of utmost importance to detect failure or defects in any part of a nuclear reactor for healthy operation of reactor as well as the safety aspects of the environment. Despite careful fabrication and manufacturing of fuel pins, there is a chance of clad failure. After fuel pin clad rupture takes place, it allows fission products to enter in to sodium pool. There are some potential consequences due to this such as Total Instantaneous Blockage (TIB) of coolant and primary component contamination. At present, the failed fuel detection techniques such as cover gas monitoring (alarming the operator), delayed neutron detection (DND-automatic trip) and standalone failed fuel localization module (FFLM) are exercised in various reactors. The first technique is a quantitative measurement of increase in the cover gas activity background whereas DND system causes automatic trip on detecting certain level of activity during clad wet rupture. FFLM is subsequently used to identify the failed fuel subassembly. The later although accurate, but mainly suffers from downtime and reduction in power during identification process. The proposed scheme, reported in this paper, reduces the operation of FFLM by predicting the faulty sector and therefore reducing reactor down time and thermal shocks. The neutron evolution pattern gets modulated because fission products are the delay neutron precursors. When they travel along with coolant to Intermediate heat Exchangers, experienced three effects i.e. delay; decay and dilution which make the neutron pulse frequency vary depending on the location of failed fuel sub assembly. This paper discusses the method that is followed to study the frequency domain properties, so that it is possible to detect exact fuel subassembly failure online, before the reactor automatically trips. (author)
Additional details
Publishing Information
- Publisher
- Bhabha Atomic Research Centre
- Imprint Place
- Mumbai (India)
- Imprint Title
- Proceedings of the symposium on advanced measurement techniques and instrumentation: abstract book
- Imprint Pagination
- 105 p.
- Journal Page Range
- p. 77
Conference
- Title
- symposium on advanced measurement techniques and instrumentation
- Acronym
- SAMTI-2011
- Dates
- 2-4 Feb 2011
- Place
- Mumbai (India)
INIS
- Country of Publication
- India
- Country of Input or Organization
- India
- INIS RN
- 43010288
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FAILURE MODE ANALYSIS; FUEL PINS; NEUTRON DETECTORS; ON-LINE SYSTEMS; POOL TYPE REACTORS; REACTOR SAFETY
- Descriptors DEC
- FUEL ELEMENTS; MEASURING INSTRUMENTS; RADIATION DETECTORS; REACTOR COMPONENTS; REACTORS; SAFETY; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 1 ref.