Humboldt Bay License Termination Plan
Humboldt Bay License Termination Plan
The license termination plan for Humboldt Bay owned by the Pacific Gas and Electric Company.
The license termination plan for Humboldt Bay owned by the Pacific Gas and Electric Company.
This manual discusses the routines to estimate radiological doses from normal operations used in
Version 6.0 of the Total System Model (TSM) as described in the TSM User Manual prepared
for the U.S. Department of Energy (DOE) by Bechtel SAIC Company (BSC) (BSC 2007a). The
TSM estimates doses during the simulation of the Civilian Radioactive Waste Management
System (CRWMS) mission. The TSM is not intended to provide a robust dose evaluation tool
and should only be used for relative comparisons of scenarios to general understand if doses are
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
The objective of this safety requirements publication is to set down the protection objectives and criteria for geological disposal and to establish the requirements that must be met to ensure the safety of this disposal option, consistent with the established principles of safety for radioactive waste management.
The purpose of this calculation is to estimate the probability of misloading a commercial spent
nuclear fuel waste package with a fuel assembly(s) that has a reactivity (i.e., enrichment and/or
burnup) outside the waste package design. The waste package designs are based on the expected
commercial spent nuclear fuel assemblies and previous analyses (Macheret, P. 2001, Section 4.1
and Table 1). For this calculation, a misloaded waste package is defined as a waste package that
This letter is written by Former Wyoming Governor Mike Sullivan to inform the Fremont County Commissioners of his conclusion to decline the MRC facility.
About 20,000 metric tons of spent, or used, nuclear
fuel have accumulated since the beginning of commercial
nuclear power prbduction in the United States. At the end
of the currently licensed period of all existing nuclear power
plants and those under construction, the amount of spent
nuclear fuel is expected to total 87,000 metric tons.
Thus far, practically all of the spent nuclear fuel is
stored in water-filled pools at reactor sites. However, space
does not exist in the pools to store all the spent fuel expected
As part of the plutonium waste form development and down-select process, repository analyses have been conducted to evaluate the long-term performance of these forms for repository acceptance. Intact and degraded mode criticality analysis of mixed oxide (MOX) spent fuel is presented in Volume I, while Volume II presents the evaluations of the waste form containing plutonium immobilized in a ceramic matrix.
To achieve energy security and greenhouse gas (GHG) emission reduction objectives, the United States must develop and deploy clean, affordable, domestic energy sources as quickly as possible. Nuclear power will continue to be a key component of a portfolio of technologies that meets our energy goals. This document provides a roadmap for the Department of Energy’s (DOE’s) Office of Nuclear Energy (NE) research, development, and demonstration activities that will ensure nuclear energy remains viable energy option for the United States.
In February, 2011 the Blue Ribbon Commission (BRC) on America’s Nuclear Future requested the Department of Energy
(DOE) to provide a white paper summarizing the quantities and characteristics of potential waste generated by various
nuclear fuel cycles. The BRC request expressed interest in two classes of radioactive wastes:
Existing waste that are or might be destined for a civilian deep geologic repository or equivalent.
Potential future waste, generated by alternative nuclear fuel cycles (e.g. wastes from reprocessing, mixed-oxide
The effective termination of the Yucca Mountain program by the U.S. Administration in 2009
has further delayed the construction and operation of a permanent disposal facility for used fuel
and high level radioactive waste (HLW) in the United States. In concert with this decision, the
President directed the Energy Secretary to establish the Blue Ribbon Commission on America’s
Nuclear Future to review and provide recommendations on options for managing used fuel and
This report evaluates the relative economics of alternative fuel cycles compared to the current
U.S. once-through fuel cycle, including concepts under consideration by the U.S. Department of
Energy’s (DOE) Global Nuclear Energy Partnership (GNEP). EPRI utilized a model developed
by the Nuclear Energy Agency (NEA), Steady-state analysis Model for Advanced Fuel Cycle
Schemes (SMAFS), to evaluate fuel cycle alternatives. The report also evaluates potential
financing options for a fuel recycling facility. Please note that this report contains preliminary
This report evaluates the radiological impacts during postulated accidents associated with the
transportation of spent nuclear fuel to the proposed Yucca Mountain repository, using the
RADTRAN 5.5 computer code developed by Sandia National Laboratories. RADTRAN 5.5 can
be applied to estimate the risks associated both with incident-free transportation of radioactive
materials as well as with accidents that may be assumed to occur during transportation. Incidentfree
transportation risks for transport of spent nuclear fuel to Yucca Mountain were evaluated in
This report presents the results of a dynamic simulation analysis for deployment of advanced light water reactors (LWRs) and fast burner reactors, as proposed by the Global Nuclear Energy Partnership (GNEP) program. Conditions for the analysis were selected for their potential to challenge the nuclear fuel simulation codes that were used, due to the large variations in nuclear fuel composition for the burner reactors before equilibrium conditions are approached. The analysis was performed in a U.S.
The IAEA has published guidance on particular elements of radioactive waste and spent fuel management,
such as establishing nuclear technical and regulatory infrastructure, relevant financing schemes, national policy
and strategies, multinational approaches and other aspects linked to building nuclear power plants. The present
publication is intended to provide a concise summary of key issues related to the development of a sound radioactive
waste and spent nuclear fuel management system. It is designed to brief countries with small or newly established
<div class="page" title="Page 1">
<div class="section">
<div class="layoutArea">
<div class="column">
<div class="page" title="Page 2">
<div class="layoutArea">
<div class="column">
<div class="page" title="Page 8">
<div class="layoutArea">
<div class="column">
This study provides a technical basis for informing policy decisions regarding strategies for the management and permanent disposal of spent nuclear fuel (SNF) and high-level radioactive waste (HLW) in the United States requiring geologic isolation. Relevant policy questions this study can help inform include the following: Is a “one-size-fits–all” repository a good strategic option for disposal? Do
The main question before the Transportation and Storage Subcommittee was whether the United States should change its approach to storing and transporting spent nuclear fuel (SNF) and high-level radioactive waste (HLW) while one or more disposal facilities are established.
This is a copy of the non-proprietary version of Revision 15 of the HI-STAR 100 safety analysis report (SAR). This version of the SAR contains information pertinent to the Humboldt Bay specific MPC-HB canister and the HI-STAR 100 HB transportation cask.
The Fukushima nuclear event of March 2011 dramatically revealed the potential risks of holding significant spent nuclear fuel at wet pools requiring continuous water circulation to maintain safe cooling. The housings for four spent fuel pools were badly damaged, and all pools lost cooling and nearly suffered fuel exposure. These conditions had the potential to result in catastrophic radiation release, rivaling or exceeding safety concerns over the nuclear reactors themselves.
This is the final report for the Argonne National Laboratory-East (ANL-E) Building 200
M-Wing Hot Cells Decontamination Project. The purpose of the project was to practically eliminate
the radioactive emissions of Rn-220 to the environment and to restore the hot cells to an empty
restricted use-condition. About 96.2 TBq (2,600 curies) per year of Rn-220 was being emitted at the
start of the project from the radioactive contaminants left in the hot cells at the end of the ANL-E
Proof-of-Breeding program work in 1985.
This is the final report for the Argonne National Laboratory-East (ANL-E) Building 200
M-Wing Hot Cells Decontamination Project. The purpose of the project was to practically eliminate
the radioactive emissions of Rn-220 to the environment and to restore the hot cells to an empty
restricted use-condition. About 96.2 TBq (2,600 curies) per year of Rn-220 was being emitted at the
start of the project from the radioactive contaminants left in the hot cells at the end of the ANL-E
Proof-of-Breeding program work in 1985.
The Cyclic Integrated Reversible-Bending Fatigue Tester (CIRFT) can be used for
investigating the vibration integrity of spent nuclear fuel during transportation.This report is the R&D 100 submission related to the CIRFT.