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Data

Dose Rate Calculations for the 2-MCO/2-DHLW Waste Package

Author(s)

OCRWM

Publication Date

October 1, 2000

The objective of this calculation is to determine the dose rates on the external surfaces of the waste package (WP) containing two Hanford defense high-level waste (DHLW) glass canisters and two Hanford multi-canister overpacks (MCO). Each MCO is loaded with the N Reactor spent nuclear fuel (SNF). The information provided by the sketches attached to this calculation is that of the potential design for the WP type considered in this calculation.

Data

Dissolved Concentration Limits of Elements with Radioactive Isotopes

Author(s)

Sandia National Laboratories

Publication Date

September 1, 2007

The purpose of this study is to evaluate dissolved concentration limits (also referred to as solubility limits) of elements with radioactive isotopes under probable repository conditions, based on geochemical modeling calculations using geochemical modeling tools, thermodynamic databases, field measurements, and laboratory experiments.

yucca mountain radionuclides dose calculation isotopic concentrations engineered barrier system geochemical analysis

Data

Dissolved Concentration Limits of Elements with Radioactive Isotopes

Author(s)

Sandia National Laboratories

Publication Date

September 1, 2007

yucca mountain radiochemical analysis storage radionuclides dose calculation isotopic concentrations

Data

Direct Radiation Dose Consequence Calculation for Category 1 and 2 Event Sequences

Author(s)

Georgeta Radulescu

Publication Date

April 1, 2005

Performance objectives for the geologic repository operations area through permanent closure in 10 CFR 63.111 identify compliance with regulatory dose limits for workers and members of the public as a design objective. The purpose of this design calculation is to determine direct radiation dose consequences for Category 1 and 2 event sequences. It does not include worker dose assessment for recovery operations following Category 1 event sequences.

high level waste spent fuel yucca mountain dose calculation naval spent nuclear fuel used fuel

SED Publication Type

Document

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Brazilian National Report

Author

Comissiio Nacional de Energia Nuclear (CNEN) ,

Industrias Nucleares Brasileiras (INB) ,

Eletrobras Termonuclear SA. (ELETRONUCLEAR) ,

Instituto Brasileiro do Meio Ambiente e dos Recursos Naturais Renovaveis (IBAMA) ,

Centro de Tecnologico da Marinha em Siio Paulo (CTMSP) ,

Ministirio da Ciencia e Tecnologia (MCT) ,

Ministirio de Relacoes Exteriores (MRE)

Publication Date

May 1, 2006

On 29 September 1997 the Join Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management was open for signature at the headquarters of the International Atomic Energy Agency in Vienna. Brazil signed the Convention on October 11th, 1997 and ratified it by the Legislative Decree n. 1.019 of November 14th, 2005. Brazil deposited the instrument of ratification with the Depositary on 17 February 2006. The Convention objectives are to achieve and maintain a high level of nuclear safety worldwide in spent fuel and radioactive waste management.

siting national report joint convention spent fuel management brazil radioactive waste management

SED Publication Type

Document

National Report of Brazill 2011 for the 4th Review Meeting of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management

Author

Comissão Nacional de Energia Nuclear (CNEN) ,

Indústrias Nucleares do Brasil S.A. (INB) ,

Eletrobrás Termonuclear - Eletronuclear S.A. (ETN) ,

Instituto Brasileiro do Meio Ambiente e dos Recursos Naturais Renováveis (IBAMA) ,

Centro Tecnológico da Marinha em São Paulo (CTMSP) ,

Ministério da Ciência e Tecnologia (MCT) ,

Ministério de Relações Exteriores (MRE)

Publication Date

October 1, 2011

On 29 September 1997, the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management was open for signature at the headquarters of the International Atomic Energy Agency in Vienna. Brazil signed the Convention on October 11th, 1997 and ratified it by the Legislative Decree 1019 of November 14th, 2005. Brazil deposited the instrument of ratification with the Depositary on 17 February 2006.

siting national report joint convention spent fuel management brazil radioactive waste management

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Siting Experience Documents Only

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Keywords

Dose Rate Calculations for the 2-MCO/2-DHLW Waste Package

Data

Dose Rate Calculations for the 2-MCO/2-DHLW Waste Package

Dissolved Concentration Limits of Elements with Radioactive Isotopes

Data

Dissolved Concentration Limits of Elements with Radioactive Isotopes

Dissolved Concentration Limits of Elements with Radioactive Isotopes

Data

Dissolved Concentration Limits of Elements with Radioactive Isotopes

Direct Radiation Dose Consequence Calculation for Category 1 and 2 Event Sequences

Data

Direct Radiation Dose Consequence Calculation for Category 1 and 2 Event Sequences

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Brazilian National Report

Document

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Brazilian National Report

National Report of Brazill 2011 for the 4th Review Meeting of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management

Document

National Report of Brazill 2011 for the 4th Review Meeting of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management