Conveners
Safety of Research Reactors
- Jose Lolich (Instituto Balseiro (Argentina))
Safety of Research Reactors
- Hassan ABOU YEHIA (Institut de Radioprotection et de Sûreté Nucléaire (IRSN) - FRANCE)
Safety of Research Reactors
- David Newland (Canadian Nuclear Safety Commission (CNSC))
Safety of Research Reactors
- Walid ZIDAN
Mr
Amgad Shokr
(Reserach Reactor Safety Section, IAEA)
17/11/2015, 09:00
Safety of Research Reactors
Oral Presentation
For more than sixty years research reactors has been a corner stone in the development and application of nuclear science and technology and in education and training of nuclear scientists and engineers. The benefits of research reactors also extended to many other fields including medical and industrial applications. Research reactors also can play an important role for building the technical...
Dr
HASSAN ABOU YEHIA
(Institut de Radioprotection et de Sûreté Nucléaire, Nuclear Safety Division)
17/11/2015, 09:30
Safety of Research Reactors
Oral Presentation
Following the Fukushima-Daiichi NPP accident which occurred on 11 March 2011, specific safety reassessments (called Complementary Safety Assessments or Stress Tests) were initiated in many countries for research reactors on requests of the regulatory bodies or decisions of the operating organizations. Their main objective was to take into account the feedback and preliminary lessons learned...
Mr
Kato Tomoaki
17/11/2015, 10:00
Safety of Research Reactors
Oral Presentation
JRR-3 at Tokai site of JAEA was in its regular maintenance period, when the Great East Japan Earthquake took place on 11th March 2011. The reactor building with the solid foundations and the equipment important to safety survived the earthquake without serious damage, and no radioactive leakage has been occurred. Recovery work, check and test of the integrity for all components have been...
Mr
Chandrashekahr Karhadkar
(Bhabha Atomic Research Centre)
17/11/2015, 11:10
Safety of Research Reactors
Oral Presentation
Dhruva is a 100 MW research reactor fuelled with natural uranium and cooled and moderated with heavy water. It is located in Bhabha Atomic Research Centre, Mumbai, it was commissioned in 1985.
Following the Fukushima Daiichi nuclear accident a complete review of existing system configuration was undertaken to ascertain reactor’s capabilities to withstand extreme natural event, like...
Mr
Emmanuel GROLLEAU
(Institute of Radioprotection and Nuclear Safety (IRSN))
17/11/2015, 11:30
Safety of Research Reactors
Oral Presentation
Following the accident that occurred on the Fukushima Daiichi nuclear power plant on the 11th March 2011, the French Prime minister asked the national nuclear safety authority (ASN) to engage a targeted reassessment of the safety of every basic nuclear facility with the aim of evaluating their capacity to withstand extreme situations beyond design basis assumptions. These specific...
Dr
Yacov Barnea
(NLSO - IAEC)
17/11/2015, 11:50
Safety of Research Reactors
Oral Presentation
N. Hazensprung (1), T. Makmal (1) and Y. Barnea (2)
(1) IRR-1, SNRC, Yavne, ISRAEL, 88000.
(2) NLSO/IAEA, Tel-Aviv, ISRAEL, 61070.
Following the accident in the Fukushima-Daiichi, Japan NPPs (March 2011), the previous ICRR in Rabat, Morocco (November 2011), recommended that the operating organizations will take a proactive approach to examining their design basis and safety analysis to...
Mr
SM MALAKA
(NECSA)
17/11/2015, 12:10
Safety of Research Reactors
Oral Presentation
Following the Fukushima nuclear accident, a directive from South Africa’s National Nuclear Regulator was received which required a safety reassessment of the SAFARI 1 research reactor.
The safety reassessment consisted of:
• Evaluation of the response of the SAFARI 1 Research Reactor when facing a set of extreme external events (EEE) and
• Verification of the preventive and...
Dr
Yassine Boulaich
(CNESTEN)
17/11/2015, 12:30
Safety of Research Reactors
Oral Presentation
In this study we have calculated some important thermal–hydraulic parameters of the Moroccan 2-MW TRIGA MARK operating under normal condition. We have also presented the analysis of some abnormal situation; the small break loss-of-coolant transients in this pool-type research reactor, with SCRAM disabled, is simulated based on the PARET model previously established and validated for our TRIGA...
Alexander Sapozhnikov
(Deputy of Department Head)
19/11/2015, 09:00
Safety of Research Reactors
Oral Presentation
To ensure the effective fulfillment by operator of national and international safety requirements, the systematic safety reassessments of the Nuclear Research Facility (NRF) should be performed periodically on the basis of graded approach with due account to potential hazard associated with a specific facility.
The regulatory body establishes frequency of the safety assessments to be...
Dr
Johannes Sterba
(Atominstitut, Vienna University of Technology)
19/11/2015, 09:50
Safety of Research Reactors
Oral Presentation
The concept of a ten year safety assessment (Periodic Safety Assessment, PSA) of a nuclear facility was introduced into Austrian legislation only in 2011, resulting in a deadline for a first such assessment by the end of 2014 for existing facilities.
The content of the PSA as laid down in the regulations consists of
- The current Safety Report of the facility
- Presentation of the current...
Ms
Justyna Adamczyk
(National Atomic Energy Agency)
19/11/2015, 10:10
Safety of Research Reactors
Oral Presentation
The National Atomic Energy Agency (PAA) in Poland undergone the IAEA Integrated Safety Assessment of Research Reactors (INSARR) mission dedicated for the Maria research reactor during the period from 31 March to 4 April 2014.
Maria reactor is located is in the city of Swierk, 30 km from the city of Warsaw. It is a tank-in-pool, multipurpose, cooled and moderated by light water and...
Mr
Alexander Adams Jr
(U.S. Nuclear Regulatory Commission)
19/11/2015, 11:00
Safety of Research Reactors
Oral Presentation
The concept of a graded approach is a basic aspect of the International Atomic Energy Agency (IAEA) for maintaining safety at research reactors. A graded approach is also a fundamental aspect of the regulation of research and test reactors (also called non-power reactors) by the U.S. Nuclear Regulatory Commission (NRC). The purpose in applying a graded approach is to match the degree of...
Ms
Farhana Naseer
(Pakistan Nuclear Regulatory Authority)
19/11/2015, 11:30
Safety of Research Reactors
Oral Presentation
Operating experience of research reactors in Pakistan is spread over a span of five decades starting with the operation of Pakistan Research Reactor-1 (PARR-1) in 1965. Research reactors are being used in Pakistan for the purpose of training and production of radioisotopes. Pakistan Nuclear Regulatory Authority (PNRA) is entrusted to ensure that a high level of safety is maintained through an...
Mr
Julius Ejembi
(Nigerian Nuclear Regulatory Authority), Mrs
Moyosola Abubakar
(Nigerian Nuclear Regulatory Authority)
19/11/2015, 12:10
Safety of Research Reactors
Oral Presentation
Nigeria is one of many countires that are developing infrastructure in nuclear energy. Challenges in developing its safety infrastucture are thus enormous. The Nigerian Government under the Nuclear Safety and Radiation Protection Act 19 of 1995 established the Nigerian Nuclear Regulatory Authority as the regulatory body responsible for nulear and radiological protection and also the regulation...
