Lifetime of a prompt-neutron generation in a research reactor with a heavy-water reflector

Atomic Energy ◽  
1995 ◽  
Vol 79 (6) ◽  
pp. 863-865 ◽  
Author(s):  
A. N. Erykalov ◽  
V. V. Kyz'minov ◽  
Yu. V. Petrov
Keyword(s):  
Heavy Water ◽  
Research Reactor ◽  
Prompt Neutron ◽  
Neutron Generation

scholarly journals Kinetic parameters study based on burn-up for improving the performance of research reactor equilibrium core

2014 ◽  
Vol 29 (4) ◽  
pp. 253-258 ◽  
Author(s):  
Atta Muhammad ◽  
Masood Iqbal ◽  
Tayyab Mahmood
Keyword(s):  
Kinetic Parameters ◽  
Generation Time ◽  
Research Reactor ◽  
Prompt Neutron ◽  
Neutron Generation ◽  
Delayed Neutron ◽  
Fuel Burn ◽  
Hard Spectrum ◽  
Computer Codes ◽  
Enriched Uranium

In this study kinetic parameters, effective delayed neutron fraction and prompt neutron generation time have been investigated at different burn-up stages for research reactor's equilibrium core utilizing low enriched uranium high density fuel (U3Si2-Al fuel with 4.8 g/cm3 of uranium). Results have been compared with reference operating core of Pakistan research Reactor-1. It was observed that by increasing fuel burn-up, effective delayed neutron fraction is decreased while prompt neutron generation time is increased. However, over all ratio beff/L is decreased with increasing burn-up. Prompt neutron generation time L in the understudy core is lower than reference operating core of reactor at all burn-up steps due to hard spectrum. It is observed that beff is larger in the understudy core than reference operating core of due to smaller size. Calculations were performed with the help of computer codes WIMSD/4 and CITATION.

Calculation of neutron generation time with prompt neutron density decay method

2013 ◽  
Vol 25 (1) ◽  
pp. 237-240 ◽  
Author(s):  
张良 Zhang Liang ◽  
陈伟 Chen Wei ◽  
赵柱民 Zhao Zhumin ◽  
张信一 Zhang Xinyi ◽  
江新标 Jiang Xinbiao
Keyword(s):  
Generation Time ◽  
Prompt Neutron ◽  
Neutron Density ◽  
Neutron Generation

Comparison of semi-heavy water and H2O as coolant for a conceptual research reactor from the view point of neutronic parameters

2020 ◽  
Vol 118 ◽  
pp. 103126 ◽  
Author(s):  
Ghasem Rahimi ◽  
Kamal Hadad ◽  
Mohammadreza Nematollahi ◽  
Ehsan Zarifi ◽  
Sumer Sahin
Keyword(s):  
Heavy Water ◽  
Research Reactor ◽  
View Point ◽  
Neutronic Parameters ◽  
Conceptual Research

The Nuclear Trade

Worldview ◽  
1984 ◽  
Vol 27 (3) ◽  
pp. 21-22
Author(s):  
Daniel Poneman
Keyword(s):  
United States ◽  
Heavy Water ◽  
Research Reactor ◽  
Nuclear Explosion ◽  
The United States ◽  
West Germany ◽  
Spent Fuel ◽  
Indian Government ◽  
International Safeguards ◽  
Nuclear Assistance

In May, 1974, the Indian Government detonated a "peaceful nuclear explosion." The device contained heavy water supplied by the United States and plutonium that had been reprocessed from the spent fuel of a research reactor supplied by Canada. That event shocked the governments involved in international nuclear commerce into greater efforts to prevent the diversion of civil nuclear assistance to military purposes. By 1976, France and West Germany had joined the United States in pledging not to export facilities for the production of plutonium. Two years later the major suppliers agreed upon guidelines intended to ensure that international safeguards would be applied to all sensitive nuclear exports.

A conceptual design for a generic heavy water research reactor to a more proliferation-resistant reactor

2018 ◽  
Vol 112 ◽  
pp. 418-430
Author(s):  
Fatemeh Mansourzadeh ◽  
Farrokh Khoshahval ◽  
Jaber Safdari
Keyword(s):  
Conceptual Design ◽  
Heavy Water ◽  
Research Reactor ◽  
Water Research

scholarly journals A multi-physics analysis for the actuation of the SSS in opal reactor

2018 ◽  
Vol 4 ◽  
pp. 8
Author(s):  
Diego Ferraro ◽  
Patricio Alberto ◽  
Eduardo Villarino ◽  
Alicia Doval
Keyword(s):  
Experimental Data ◽  
Heavy Water ◽  
Research Reactor ◽  
Three Dimensional ◽  
Water Drainage ◽  
Hydraulic Behaviour ◽  
Component Design ◽  
Definition Of ◽  
Safety Features ◽  
Temporal Profiles

OPAL is a 20 MWth multi-purpose open-pool type Research Reactor located at Lucas Heights, Australia. It was designed, built and commissioned by INVAP between 2000 and 2006 and it has been operated by the Australia Nuclear Science and Technology Organization (ANSTO) showing a very good overall performance. On November 2016, OPAL reached 10 years of continuous operation, becoming one of the most reliable and available in its kind worldwide, with an unbeaten record of being fully operational 307 days a year. One of the enhanced safety features present in this state-of-art reactor is the availability of an independent, diverse and redundant Second Shutdown System (SSS), which consists in the drainage of the heavy water reflector contained in the Reflector Vessel. As far as high quality experimental data is available from reactor commissioning and operation stages and even from early component design validation stages, several models both regarding neutronic and thermo-hydraulic approaches have been developed during recent years using advanced calculations tools and the novel capabilities to couple them. These advanced models were developed in order to assess the capability of such codes to simulate and predict complex behaviours and develop highly detail analysis. In this framework, INVAP developed a three-dimensional CFD model that represents the detailed hydraulic behaviour of the Second Shutdown System for an actuation scenario, where the heavy water drainage 3D temporal profiles inside the Reflector Vessel can be obtained. This model was validated, comparing the computational results with experimental measurements performed in a real-size physical model built by INVAP during early OPAL design engineering stages. Furthermore, detailed 3D Serpent Monte Carlo models are also available, which have been already validated with experimental data from reactor commissioning and operating cycles. In the present work the neutronic and thermohydraulic models, available for OPAL reactor, are coupled by means of a shared unstructured mesh geometry definition of relevant zones inside the Reflector Vessel. Several scenarios, both regarding coupled and uncoupled neutronic & thermohydraulic behavior, are presented and analyzed, showing the capabilities to develop and manage advanced modelling that allows to predict multi-physics variables observed when an in-depth performance analysis of a Research Reactor like OPAL is carried out.

HAZOP-study on heavy water research reactor primary cooling system

2010 ◽  
Vol 37 (3) ◽  
pp. 428-433 ◽  
Author(s):  
M. Hashemi-Tilehnoee ◽  
A. Pazirandeh ◽  
S. Tashakor
Keyword(s):  
Heavy Water ◽  
Research Reactor ◽  
Cooling System ◽  
Water Research
Sign in / Sign up

Export Citation Format

Share Document