NUR research reactor safety analysis study for long time natural convection (NC) operation mode

2010 ◽  
Vol 240 (4) ◽  
pp. 823-831 ◽  
Author(s):  
M. Azzoune ◽  
L. Mammou ◽  
M.H. Boulheouchat ◽  
T. Zidi ◽  
M.Y. Mokeddem ◽  
...  
Keyword(s):  
Natural Convection ◽  
Research Reactor ◽  
Operation Mode ◽  
Safety Analysis ◽  
Reactor Safety ◽  
Analysis Study ◽  
Long Time

scholarly journals Application of best estimate plus uncertainty in review of research reactor safety analysis

2015 ◽  
Vol 30 (1) ◽  
pp. 75-82 ◽  
Author(s):  
Simon Adu ◽  
Ivan Horvatovic ◽  
Emmanuel Darko ◽  
Geoffrey Emi-Reynolds ◽  
Francesco D'auria
Keyword(s):  
Regulatory Authority ◽  
Research Reactor ◽  
Safety Analysis ◽  
Regulatory Body ◽  
Reactor Safety ◽  
Operational Conditions ◽  
Safety Requirements ◽  
Best Estimate ◽  
Safety Margins ◽  
Realistic Information

To construct and operate a nuclear research reactor, the licensee is required to obtain the authorization from the regulatory body. One of the tasks of the regulatory authority is to verify that the safety analysis fulfils safety requirements. Historically, the compliance with safety requirements was assessed using a deterministic approach and conservative assumptions. This provides sufficient safety margins with respect to the licensing limits on boundary and operational conditions. Conservative assumptions were introduced into safety analysis to account for the uncertainty associated with lack of knowledge. With the introduction of best estimate computational tools, safety analyses are usually carried out using the best estimate approach. Results of such analyses can be accepted by the regulatory authority only if appropriate uncertainty evaluation is carried out. Best estimate computer codes are capable of providing more realistic information on the status of the plant, allowing the prediction of real safety margins. The best estimate plus uncertainty approach has proven to be reliable and viable of supplying realistic results if all conditions are carefully followed. This paper, therefore, presents this concept and its possible application to research reactor safety analysis. The aim of the paper is to investigate the unprotected loss-of-flow transients "core blockage" of a miniature neutron source research reactor by applying best estimate plus uncertainty methodology. The results of our calculations show that the temperatures in the core are within the safety limits and do not pose any significant threat to the reactor, as far as the melting of the cladding is concerned. The work also discusses the methodology of the best estimate plus uncertainty approach when applied to the safety analysis of research reactors for licensing purposes.

Operator reliability study for Probabilistic Safety Analysis of an operating research reactor

2015 ◽  
Vol 80 ◽  
pp. 409-415 ◽  
Author(s):  
F. Mohamed ◽  
A. Hassan ◽  
R. Yahaya ◽  
I. Rahman ◽  
M. Maskin ◽  
...  
Keyword(s):  
Research Reactor ◽  
Safety Analysis ◽  
Reliability Study ◽  
Probabilistic Safety

Evaluation of computational fluid dynamic methods for reactor safety analysis (ECORA)

2005 ◽  
Vol 235 (2-4) ◽  
pp. 359-368 ◽  
Author(s):  
M. Scheuerer ◽  
M. Heitsch ◽  
F. Menter ◽  
Y. Egorov ◽  
I. Toth ◽  
...  
Keyword(s):  
Computational Fluid Dynamic ◽  
Fluid Dynamic ◽  
Safety Analysis ◽  
Reactor Safety ◽  
Dynamic Methods

scholarly journals MELT-III: a neutronics, thermal-hydraulics computer program for fast reactor safety analysis. Volume II

1974 ◽  
Author(s):  
A.E. Waltar ◽  
W.L. Partain ◽  
D.C. Kolesar ◽  
L.D. O'Dell ◽  
A. Jr. Padilla ◽  
...  
Keyword(s):  
Computer Program ◽  
Fast Reactor ◽  
Safety Analysis ◽  
Thermal Hydraulics ◽  
Reactor Safety

scholarly journals Determination of trace elements in some fruits collected in Vietnam and Korea by Neutron Activation Analysis on Dalat and HANARO research reactors

2015 ◽  
Vol 5 (4) ◽  
pp. 23-29
Author(s):  
Thi Sy Nguyen ◽  
Manh Dung Ho ◽  
Van Doanh Ho ◽  
Quang Thien Tran ◽  
Sam Chung Yong
Keyword(s):  
Trace Elements ◽  
Neutron Activation Analysis ◽  
Activation Analysis ◽  
Neutron Activation ◽  
Research Reactor ◽  
Standard Samples ◽  
Long Time ◽  
Polyethylene Bags ◽  
Mn Concentrations

The k0-based neutron activation analysis (k0-NAA) has been applied for determination of trace multi-element in 5 fruits: Orange, tomato, persimmon, pear and apple. The samples were collected in Vietnam and Korea, and dried-frozen in laboratory at a temperature of -650C, weighed approximately 50 mg or 100 mg each sample, and put in clean polyethylene bags for short and long time irradiations, respectively. The NIST-1547 (Peach Leaves) and IAEA-V-10 (Hay Powder) were used for the purpose of quality control. Both analytical and standard samples were irradiated in the 500 kW Dalat research reactor (Vietnam) and the 20 MW HANARO research reactor (Korea). Concentration of 16 elements: Al, As, Au, Br, Ca, Cl, Co, Eu, Fe, K, La, Mg, Mn, Na, Rb and Zn were determined. By comparison the concentrations of trace elements in the investigated Vietnam and Korea’s fruits, revealed that they are mostly similar between two places. However, the Ca concentration in orange from Vietnam was approximately 2.5 times higher than that one from Korea, whereas the Ca concentration in pear from Vietnam was approximately 21 times lower than that one from Korea. The Mn concentrations in all of fruits that collected in Vietnam were mostly higher than those collected in Korea, ranging between 1.4 to 2.2 times.

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