A proposal for an NRU loop irradiation of a "parallex" CANDU-6 geometry bundle containing natural uranium (outer ring) and 3.1% pu in depleted uranium (intermediate/inner rings).

A proposal for an NRU loop irradiation of a Author: M. R. Floyd
Publisher:
ISBN:
Category :
Languages : en
Pages : 0

Get Book Here

Book Description


A proposal for an NRU loop irradiation of a "parallex" CANDU-6 geometry bundle containing 3.1% pu in depleted uranium (intermediate/inner rings) and 1.25% dy in natural uranium (outer ring).

A proposal for an NRU loop irradiation of a Author: F. C. Dimayuga
Publisher:
ISBN:
Category :
Languages : en
Pages : 0

Get Book Here

Book Description


A proposal for an NRU loop irradiation of the first prototype low-void reactivity fuel bundle containing enriched uranium, depleted uranium and dysprosium

A proposal for an NRU loop irradiation of the first prototype low-void reactivity fuel bundle containing enriched uranium, depleted uranium and dysprosium PDF Author: C. G. Ouellet
Publisher:
ISBN:
Category :
Languages : en
Pages : 0

Get Book Here

Book Description


A proposal for an NRU loop irradiation of a canflex bundle containing 1.35% pu mox fuel in the outer and inner rings

A proposal for an NRU loop irradiation of a canflex bundle containing 1.35% pu mox fuel in the outer and inner rings PDF Author: H. B. Hamilton
Publisher:
ISBN:
Category :
Languages : en
Pages : 0

Get Book Here

Book Description


A proposal for u2 loop irradiation of the second prototype low-void reactivity fuel bundle containing enriched uranium, depleted uranium and dysprosium

A proposal for u2 loop irradiation of the second prototype low-void reactivity fuel bundle containing enriched uranium, depleted uranium and dysprosium PDF Author: C. G. Ouellet
Publisher:
ISBN:
Category :
Languages : en
Pages : 0

Get Book Here

Book Description


A proposal for an NRU loop irradiation and power ramp of two canflex mk iv high-burnup low-void-reactivity fuel (hb-LVRF) bundles containing enriched uranium, natural uranium and dysprosium

A proposal for an NRU loop irradiation and power ramp of two canflex mk iv high-burnup low-void-reactivity fuel (hb-LVRF) bundles containing enriched uranium, natural uranium and dysprosium PDF Author: M. R. Floyd
Publisher:
ISBN:
Category :
Languages : en
Pages : 0

Get Book Here

Book Description


Nuclear Energy Today

Nuclear Energy Today PDF Author: OECD Nuclear Energy Agency
Publisher: OECD
ISBN:
Category : Business & Economics
Languages : en
Pages : 120

Get Book Here

Book Description
As energy demand increases in line with the expansion of the world's leading economies and the growth of developing economies, a key challenge remains of how to provide the energy levels required while protecting our environment and conserving natural resources. Nuclear energy is a complex and controversial technology but also has the potential to provide considerable benefits. This publication explores a range of issues involved in the use of nuclear energy, including safety aspects, whether its use is economically competitive, its role in meeting greenhouse gas reduction targets, how to manage the radioactive waste it generates, whether its use increase the risk of proliferation of nuclear weapons, security of resources, and its potential role in the future.

Nuclear Fuel Cycle Simulation System (VISTA)

Nuclear Fuel Cycle Simulation System (VISTA) PDF Author: International Atomic Energy Agency
Publisher: IAEA
ISBN:
Category : Business & Economics
Languages : en
Pages : 112

Get Book Here

Book Description
The Nuclear Fuel Cycle Simulation System (VISTA) is a simulation system which estimates long term nuclear fuel cycle material and service requirements as well as the material arising from the operation of nuclear fuel cycle facilities and nuclear power reactors. It is a scenario based simulation tool which can model several nuclear fuel cycle options including existing nuclear power reactor types and future possible reactor types. The past operations of the power reactors and fuel cycle facilities can be modelled in the system, in order to estimate the current amount of spent fuel stored or total Pu in stored spent fuel. It can also accept future projections for nuclear power and other scenario parameters in order to predict future fuel cycle material requirements.The model has been designed to be an optimum mixture of simplicity, speed and accuracy. It does not require too many input parameters if the purpose is just to compare the requirements for selected scenarios. Furthermore, the accuracy of the system can be improved by introducing more detailed and correct sets of input parameters.

Yvain

Yvain PDF Author: Chretien de Troyes
Publisher: Yale University Press
ISBN: 0300038380
Category : Poetry
Languages : en
Pages : 244

Get Book Here

Book Description
A twelfth-century poem by the creator of the Arthurian romance describes the courageous exploits and triumphs of a brave lord who tries to win back his deserted wife's love

Viability of Inert Matrix Fuel in Reducing Plutonium Amounts in Reactors

Viability of Inert Matrix Fuel in Reducing Plutonium Amounts in Reactors PDF Author: International Atomic Energy Agency
Publisher: IAEA
ISBN:
Category : Business & Economics
Languages : en
Pages : 100

Get Book Here

Book Description
The reactors around the world have produced more than 2000 tonnes of plutonium, contained in spent fuel or as separated forms through reprocessing. Disposition of fissile materials has become a primary concern of nuclear non-proliferation efforts worldwide. There is a significant interest in IAEA Member States to develop proliferation resistant nuclear fuel cycles for incineration of plutonium such as inert matrix fuels (IMFs). This publication reviews the status of potential IMF candidates and describes several identified candidate materials for both fast and thermal reactors: MgO, ZrO2, SiC, Zr alloy, SiAl, ZrN; some of these have undergone test irradiations and post irradiation examination. Also discussed are modelling of IMF fuel performance and safety analysis. System studies have identified strategies for both implementation of IMF fuel as homogeneous or heterogeneous phases, as assemblies or core loadings and in existing reactors in the shorter term, as well as in new reactors in the longer term.