Curie2 combined search

Category of Content

Siting Experience Documents Only

Displaying 1 - 16 of 16

Data

Waste Package Neutron Absorber, Thermal Shunt, and Fill Gas Selection Report

Author(s)

CRWMS M&O

Publication Date

January 1, 2000

Materials for neutron absorber, thermal shunt, and fill gas for use in the waste package were selected using a qualitative approach. For each component, selection criteria were identified; candidate materials were selected; and candidates were evaluated against these criteria. The neutron absorber materials evaluated were essentially boron-containing stainless steels. Two candidates were evaluated for the thermal shunt material. The fill gas candidates were common gases such as helium, argon, nitrogen, carbon dioxide, and dry air.

Data

Geochemistry Model Validation Report: Material Degradation and Release Model

Author(s)

Sandia National Laboratories

Publication Date

September 1, 2007

The purpose of the material degradation and release (MDR) model is to predict the fate of the waste package materials, specifically the retention or mobilization of the radionuclides and the neutron-absorbing material as a function of time after the breach of a waste package during the 10,000 years after repository closure. The output of this model is used directly to assess the potential for a criticality event inside the waste package due to the retention of the radionuclides combined with a loss of the neutron-absorbing material.

yucca mountain criticality analysis neutron absorbers postclosure materials analysis radionuclide transport neutron transport

Data

EQ6 calculations for Chemical Degradation of Navy Waste Packages

Author(s)

OCRWM

Publication Date

December 1, 1999

The Monitored Geologic Repository Waste Package Operations of the Civilian Radioactive Waste Management System Management & Operating Contractor (CRWMS M&O) performed calculations to provide input for disposal of spent nuclear fuel (SNF) from the Navy (Refs. 1 and , 2). The Navy SNF has been considered for disposal at the potential Yucca Mountain site. For some waste packages, the containment may breach (Ref. 3), allowing the influx of water. Water in the waste package may moderate neutrons, increasing the likelihood of a criticality event within the waste package.

criticality yucca mountain neutron absorbers monitored geologic repository naval spent nuclear fuel waste package degradation corrosion geochemical analysis flooding cal-edc-md-000007

SED Publication Type

Web Link

JOINT CONVENTION ON THE SAFETY OF SPENT FUEL MANAGEMENT AND ON THE SAFETY OF RADIOACTIVE WASTE MANAGEMENT SECOND NATIONAL REPORT

Author

National Atomic Energy Commission

Publication Date

January 1, 2005

This report describes the actions taken in Argentina on the safety of spent fuel management
(SF) and on the safety of radioactive waste management, in order to provide evidence of the
fulfillment of its obligations under the Joint Convention. To facilitate the reading and a better
understanding of this report a summary of those parts of the 1st Report that were considered
necessary have been included.

spent fuel safety waste management joint convention argentina waste facilities used fuel

SED Publication Type

Web Link

JOINT CONVENTION ON THE SAFETY OF SPENT FUEL MANAGEMENT AND ON THE SAFETY OF RADIOACTIVE WASTE MANAGEMENT THIRD NATIONAL REPORT

Author

National Atomic Energy Commission

Publication Date

January 1, 2008

The present National Report describes the actions taken in Argentina on the safety of spent fuel
(SF) management and on the safety of radioactive waste (RW) management, in order to provide
evidence of the fulfilment of the obligations derived from the Joint Convention. To facilitate the
reading and a better understanding, it has been decided to include a summary of those parts of
the two prior National Reports that are considered necessary in order to comply with this
objective.

spent fuel radioactive waste waste management joint convention waste facilities used fuel

SED Publication Type

Web Link

JOINT CONVENTION ON THE SAFETY OF SPENT FUEL MANAGEMENT AND ON THE SAFETY OF RADIOACTIVE WASTE MANAGEMENT FOURTH NATIONAL REPORT Argentina

Author

National Atomic Energy Commission

Publication Date

January 1, 2001

The structure of the Fourth National Report complies with the Guidelines Regarding the
Form and Structure of National Reports (INFCIRC/604/Rev.1).

Section A describes the scope of the nuclear activity developed in Argentina since 1950
as well as the legal and regulatory framework. It also makes reference to the Strategic
Plan for Radioactive Waste Management (Strategic Plan), which refers to the safety of
Spent Fuel Management and Radioactive Waste Management.

disposal safety radioactive waste waste management siting storage regulations argentina waste facilities

General Reports, Various Sources, NUREGs, etc

Topical Report on Actinide-Only Burnup Credit for PWR Spent Nuclear Fuel Packages

Author(s)

DOE

Publication Date

April 1, 1997

A methodology for performing and applying nuclear criticality safety calculations, for PWR spent nuclear fuel (SNF) packages with actinide-only burnup credit, is described. The changes in the U-234, U-235, U-236, U-238, Pu-238, Pu-239, Pu-240, Pu-241, Pu-242, and Am-241 concentration with burnup are used in burnup credit criticality analyses. No credit for fission product neutron absorbers is taken. The methodology consists of five major steps. (1) Validate a computer code system to calculate isotopic concentrations of SNF created during burnup in the reactor core and subsequent decay.

criticality spent fuel fission products cross-section data safety code cooling time decay design multiplication factors neutron absorbers reactor cores nuclear fuel burnup nuclear fuel cycle benchmarks used fuel

General Reports, Various Sources, NUREGs, etc

Topical Report on Actinide-Only Burnup Credit for PWR Spent Nuclear Fuel Packages

Author(s)

Office of Civilian Radioactive Waste Management

Publication Date

April 1, 1997

criticality spent fuel fission products cross-section data benchmark safety code cooling time decay design multiplication factors neutron absorbers reactor cores nuclear fuel burnup nuclear fuel cycle used fuel

SED Publication Type

Web Link

The NUMO Structured Approach to HLW Disposal in Japan

Author

Nuclear Waste Management Organization of Japan

Publication Date

July 1, 2007

The constraints set by the Japanese HLW disposal programme – particularly associated with
the decision to initiate siting by an open call for volunteers to host a geological repository –
pose particular challenges for repository project management. In order to maintain the
flexibility required to respond to the conditions found at volunteer sites, NUMO has not
published reference designs or site characterisation plans, as is normal for programmes
progressing by site nomination. Instead, we have developed a methodology – the NUMO

disposal high level waste repository japan siting waste facilities

SED Publication Type

Web Link

JOINT CONVENTION ON THE SAFETY OF SPENT FUEL MANAGEMENT AND ON THE SAFETY OF RADIOACTIVE WASTE MANAGEMENT NATIONAL REPORT ARGENTINA 2003

Author

National Atomic Energy Commission

Publication Date

January 1, 2003

The structure of this National Report complies, to the greatest adjustment possible, with the
Guidelines Regarding the Form and Structure of National Reports approved in the
Preparatory Meeting held in Vienna in December 2001.

Section A includes a general introduction to the report, and a reference to the National
Program which contemplates spent fuel and radioactive waste management and the treatment
of wastes that originate from Mining and Uranium Processing.

spent fuel radioactive waste waste management regulations waste facilities used fuel

Data

EQ6 Calculation for Chemical Degradation of Shippingport PWR (HEU Oxide) Spent Nuclear Fuel Waste Packages

Author(s)

OCRWM

Publication Date

December 1, 1999

The Monitored Geologic Repository (MGR) Waste Package Operations (WPO) of the Civilian Radioactive Waste Management System Management & Operating Contractor (CRWMS M&O) performed calculations to provide input for disposal of spent nuclear fuel (SNF) from the Shippingport Pressurized Water Reactor (PWR) (Ref. 1). The Shippingport PWR SNF has been considered for disposal at the proposed Yucca Mountain site.

criticality yucca mountain heu neutron absorbers monitored geologic repository storage waste package design waste package degradation shippingport corrosion chemical analysis cal-edc-md-000002

Presentation

slides - Management of Spent Fuel Pool Neutron Absorbing Material Degradation

Author(s)

Wong, E.

Publication Date

May 1, 2013

Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013

spent fuel pool neutron absorbers slides nei used fuel management meeting material degradation

Data

EQ6 Calculation for Chemical Degradation of Enrico Fermi Codisposal Waste Packages: Effects of Updated Design and Rates

Author(s)

OCRWM

Publication Date

December 1, 2001

The Monitored Geologic Repository (MGR) Waste Package Project of the BSC Management and Operating Contractor for the Department of Energy's Office of Civilian Radioactive Waste Management performed calculations to provide input for disposal of spent nuclear fuel (SNF) from the Enrico Fermi Reactor owned by the DOE (Ref. 9). The Fermi SNF has been considered for disposal at the proposed Yucca Mountain site.

yucca mountain neutron absorbers monitored geologic repository storage co-disposal waste package high level waste glass fermi waste package degradation corrosion flooding cal-edc-md-000015

Data

EQ6 Calculations for Chemical Degradation of TRIGA Codisposal Waste PacKages

Author(s)

OCRWM

Publication Date

November 1, 1999

The Monitored Geologic Repository Waste Package Operations of the Civilian Radioactive Waste Management System Management & Operating Contractor (CRWMS M&O) performed calculations to provide input for disposal of spent nuclear fuel (SNF) from the Training, Research, Isotopes, General Atomics (TRIGA) reactor (Ref. 1). The TRIGA SNF has been considered for disposal at the potential Yucca Mountain site.

criticality yucca mountain neutron absorbers monitored geologic repository storage high level waste glass triga waste package design corrosion geochemical analysis cal-edc-md-000001

Data

EQ6 Calculation for Chemical Degradation of Shippingport LWBR (Th/U Oxide) Spent Nuclear Fuel Waste Packages

Author(s)

OCRWM

Publication Date

September 1, 2000

The Monitored Geologic Repository (MGR) Waste Package Department of the Civilian Radioactive Waste Management System Management & Operating contractor (CRWMS M&O) performed calculations to provide input for disposal of spent nuclear fuel (SNF) from the Shippingport Light Water Breeder Reactor (LWBR) (Ref. 1). The Shippingport LWBR SNF has been considered for disposal at the potential Yucca Mountain site.