20
NuclearPlantJournal.com Nuclear Plant Journal, July-August 2014
New
Documents
EPRI
1.
NuclearPlantPerformancePrograms
.
Product ID: 3002003984. PublishedApril
2014.
Nuclear
power
plants
are
complex systems that can provide
engineers with many operational and
maintenance challenges. The number
and variety of degradation and failure
mechanisms challenge high reliability,
and the numerous maintenance and
engineering approaches available make
it difficult to determine which offers the
greatest impact on plant performance.
Performance and reliability often can be
improved by providing engineers with
access to a collaborative environment
where thoughts, ideas, and solutions can
be readily shared.
EPRI has coordinated the Heat
Exchanger Performance Users Group
(HXPUG), Service Water Assistance
Program (SWAP), and Plant Performance
Enhancement Program (P
2
EP) for many
years to support improved nuclear plant
performance. These groups are now
available through a single supplemental
project to facilitate participant access to
their diverse benefits. The groups make
it possible for engineers to access the
nuclear fleet’s broad knowledge base and
apply it to their specific issues.
2.
Steam Generator Management
Program: Development of System
Performance Examination Technique
Specification Sheets
. Product ID:
3002002847. Published May 2014.
This report outlines the procedures
for and describes the tools to
begin developing Steam Generator
Management Program PWR (pressurized
water reactor) Examination Guidelines,
Appendix I Examination Technique
Specification Sheets. Work has been
ongoing in this area since early 2000, and
culminated with the procedures and tools
described in this report.
3.
Materials Reliability Program: Finite
Element Analysis of ThreeMile Island RC-
P-1B Drain Weld Cracking (MRP-385
).
Product ID: 3002002973. Published May
2014.
The objective of this project was
to develop a detailed three-dimensional
finite element analysis (FEA) model
of the Three Mile Island (TMI) RC-P-
1B drain line and to use that model to
evaluate the influence of weld residual
stress and thermal transient- and swirl
penetration-related thermal loading on
crack initiation and growth potential.
4.
Nuclear Maintenance Applications
Center: Complete Product List, Spring
2014
. Product ID: 3002003990. Published
May 2014.
Nuclear Maintenance Applications
Center: Complete Product List (Spring
2014) is a comprehensive list of
products, workshops, and meetings
offered by EPRI’s Nuclear Maintenance
Applications Center (NMAC).
5.
Advanced Nuclear Technology: Alloy
690SteamGeneratorTubingSpecification
Sourcebook
. Product ID: 3002003124.
Published June 2014.
This revised document provides
requirements and recommendations for
procuring Alloy 690 steam generator
tubing and sleeve material.
6.
Welding and Repair Technology
for Power Plants, 11th International
EPRI Conference Program
. Product ID:
3002004164. Published June 2014.
This is the program for the Welding
and Repair Technology for Power Plants
11th International EPRI Conference. The
three-day meeting held on June 25–27,
2014 in Naples, Florida addressed the
repair of nuclear, fossil, heat recovery
steam generator (HRSG), and steam
turbine power plant components. Topics
for discussion included repair methods,
performance, prior service effects, repair
and welding qualifications, materials
properties, advanced repair technology,
corrosion, and case histories.
7.
Out-of-Reactor Corrosion Tests of
Fuel Cladding Materials: Corrosion as
a Function of Hydrogen Overpressure
.
Product ID: 3002004140. Published June
2014.
EPRI has sponsored laboratory
experiments to investigate whether an
increased dissolved hydrogen (DH) level
in the reactor coolant of pressurized
water reactors (PWR) would result in
increased hydrogen pickup (HPU) by the
fuel cladding and spacer weld structure
materials. This report documents exposure
of clean, modern zirconium-based alloys
for up to 730 days at three DH levels as
well as exposure of Zircaloy 4 (Zry-4)
specimens with different types of nickel
contacts for 100 days at three DH levels.
8.
Comanche Peak Grid Tab Hot Cell
Examinations
. Product ID: 3002003065.
Published June 2014.
ZIRLO grid tabs from a U.S. pressurized
water reactor (PWR) were analyzed for
hydrogen pickup and oxide thickness as a
function of operating parameters and axial
position. Grid tab samples were obtained
from two assemblies, each exposed for
three cycles: one fuel assembly that was
exposed to elevated Li (pH) for all three
cycles and another that was exposed to
elevated Li (pH) for one cycle. The two
issues addressed by this project were: the
potential for excessive rod corrosion and
thepossible embrittlement of tabs resulting
from grid oxide and hydrogen absorption.
In this report, the hot cell analysis results
of the grid tabs are presented to help
address grid tab embrittlement. Previous
work eliminated concern for excessive
rod corrosion (EPRI report 3002000693).
9.
CORAL Design Review
. Product ID:
3002002909. Published July 2014.
The EPRI Fuel Reliability Program
has been developing a boiling water
reactor (BWR) crud deposition model and
risk assessment tool (CORAL) to predict
tenacious crud deposition and to assess
the risk for crud-induced fuel cladding
corrosion issues. CORAL development
is near completion, and CORAL should
be delivered to utilities in the near future.
As part of the code development process,
an expert review meeting was conducted
on August 20–21, 2013, by independent
industry experts to review and critique the
CORAL models and to develop ideas for
improvements for future revisions. The
purpose of this report is to summarize
the expert review meeting and list the
independent expert recommendations.
The above EPRI documents may be
ordered by contacting the Order Center
at (800) 313-3774, Option 2, or email at
.
