Argentina (IRAM) Belgium (NBN) Canada (SCC) China (SAC) Finland (SFS) France (AFNOR) Germany (DIN) India (BIS) Iran, Islamic Republic of (ISIRI) Italy (UNI) Japan (JISC)
Korea, Republic of (KATS) Netherlands (NEN) Pakistan (PSQCA) Russian Federation (GOST R) Spain (AENOR) Sweden (SIS) Switzerland (SNV) Ukraine (DTR) United Kingdom (BSI) United States (ANSI)
3
Observing Countries (5): Bulgaria (BDS) Hungary (MSZT) Poland (PKN) Romania (ASRO) Turkey (TSE)
Scope: The scope includes siting, design, construction, operation and decommissioning.
Siting includes all types of nuclear installations and all topics such as flooding, seismic hazards, etc.
Research reactors include a large variety of facilities : production of neutron beams, irradiation of specimens, production of isotopes (especially production for nuclear medicine) and test reactors or prototypes of new technologies.
Excluded : decommissioning is limited to technical topics that are specific to reactors.
5
Five (5) published standards under the direct responsibility of SC 6.
ISO 6527:1982 Nuclear Power Plants—Reliability Data Exchange—General Guidelines
ISO 7385:1983 Nuclear Power Plants—Guidelines to Ensure Quality of Collected Data on Reliability
ISO 8107:1993 Nuclear Power Plants—Maintainability—Terminology
ISO 10645:1992 Nuclear Energy—Light Water Reactors—Calculation of the Decay Heat Power in Nuclear Fuels
ISO 10979:1994 Identification of Fuel Assemblies for Nuclear Power Reactors
Standard Withdrawn (1) ISO 6258:1985 Nuclear Power Plants—Design Against Seismic
Hazards
6
SC 6, Reactor Technology
WG 1
Power Reactor Analyses
and Measurements
TC 85, Nuclear Energy, Nuclear
Technologies, & Radiological Protection
INTERNATIONAL ORGANIZATION OF STANDARDIZATION
WG 2
Research and Test
Reactors
WG 3
Power Reactor, Siting,
Design, Operation, and
Decommissioning
PWI 10645
NP 18075
PWI 18076
NP 18077
PWI 18078
NP 18156
PWI 19492 NP 18195
NP 18229
PWI 18583
PWI 19462
ISO/NP 18075, Steady-state neutronics methods for power-reactor analysis (WG 1)
ISO/NP 18077, Reload startup physics tests for pressurized water reactors (WG 1)
ISO/NP 18156, Technical specification guide for decay heat computation codes in nuclear reactors (WG 1)
ISO/NP 18195, Method for justification of nuclear safety fire partitioning efficiency in water (WG 3)
ISO/NP 18229, Essential technical requirements for GEN IV nuclear reactors (WG 3)
ISO/NP 19226, Determination of neutron fluence and displacements per atom (dpa) in reactor vessel and internals (WG 1)
8
Ballot Type
Project #, Title Voting Summary
Combined
CIB for
concurrence
of 5 SRs
ISO 6258:1985, Nuclear power plants – Design
against seismic
ISO 6527:1982, Nuclear power plants -- Reliability
data exchange -- General guidelines
ISO 7385:1983, Nuclear power plants -- Guidelines to
ensure quality of collected data on reliability
ISO 8107:1993, Nuclear power plants --
Maintainability – Terminology
ISO 10979:1994, Identification of fuel assemblies for
nuclear power reactors
14 concurred to withdraw this standard
(3 opposed / 3 votes not cast)
14 concurred to reapprove this standard
(3 opposed / 3 votes not cast)
13 concurred to reapprove this standard
(4 opposed / 3 votes not cast)
15 concurred to reapprove this standard
(2 opposed / 3 votes not cast)
15 concurred to reapprove this standard
(2 opposed / 3 votes not cast)
9
Ballot
Type Project #, Title Voting Summary
NP 18583, Technical specifications for the
connection of mobile equipments for
emergency intervention on nuclear
installations (WG 3)
Decision: PENDING due to lack of
experts named by approving
countries
NP 19226, Determination of neutron fluence
and displacement (WG 1)
Decision: REGISTERED as active
project
PWI 19462, Assessing atmospheric effects
on ultimate heat sink (WG 3)
Status: Sufficient interest not received
to move further without additional
study
NP 19492 (formerly 21240), Technical
Specifications for Research Reactors
(WG 2)
Decision: PENDING due to lack of
experts named by approving
countries
10
To develop, maintain and promote standards covering calculation, analysis and measurements in support of physics of power reactor core design and operation. Such standards will (a) provide criteria for the selection of nuclear data and computational methods; (b) provide appropriate benchmark problem specifications for verification of calculation methods used by reactor core designers; (c) provide criteria for evaluation of accuracy and the range of applicability of data methods; (d) define methods of verification and of estimating uncertainties.
11
WG 1 Power Reactor Analyses and Measurements
Project # Title Status
10645 Decay heat power in light water reactors Stage 00.60
Although NP ballot was successful, evaluation found that
project should not be initiated until new data is available. 18075 Steady-state neutronics methods for power-
reactor analysis
Stage 10.99
NP ballot successful
Active project 18076 Nuclear data for the production of radioisotopes Stage 00.60
NP ballot did not receive sufficient experts to proceed 18077 Reload startup physics tests for pressurized water
reactors
Stage 10.99
NP ballot successful
Active project 18078 Nuclear data sets for reactor design calculations Stage 00.60
NP ballot did not receive sufficient experts to proceed 18156 Technical specification guide for decay heat
computation codes in nuclear reactors
Stage 10.99
NP ballot successful
Active project 19226 Determination of neutron fluence and
displacement
Stage 10.99
NP ballot successful
Active project
12
To develop, maintain and promote standards for the design, construction, operation, maintenance, utilization, and decommissioning of research and test reactors.
For the forthcoming years, priority will be given to operation, maintenance, utilization including refurbishment issues, dosimetry for research reactors services, and production of isotopes for nuclear medicine.
13
WG 2 Research and Test Reactors
Project # Title Status
19492
(formerly 21240)
Technical specifications for research
reactors
NP ballot issued, but criteria for approval
not met due to lack of experts named by
approving countries.
Decision: Pending
14
To develop, maintain and promote standards dealing with all topics related with the siting, design, operation and decommissioning of Power reactors.
Operation includes emergency equipments, power reactors include non-electrical applications, and transportable nuclear reactors.
Excluded: the standardization of ventilation systems (dealt with by SC 2) and technical issues of common interest for reactors and other nuclear installations (dealt with by SC 5) and topics which are within the scope of work of SC 6/ WG1
15
WG 3 Power Reactor Siting and Design
Project # Title Status
18195 Method for justification of nuclear safety
fire partitioning efficiency in water
Stage 10.99
Active project
18229 Essential technical requirements for
GEN IV nuclear reactors
Stage 10.99
Active project
18583 Technical specifications for the
connection of mobile equipments for
emergency intervention on nuclear
installation
NP ballot issued, but criteria for approval
not met due to lack of experts named
Decision: Pending
19462 Assessing atmospheric effects on
ultimate heat sink
PWI ballot issued, but sufficient interest
not received to move further without
additional study.
16
17
Accomplishments:
Improved ballot response. Average response the last year = 88%
Five (5) new projects recently initiated
Better interaction with other TC 85 subcommittees
Concerns:
Approving members fail to name an expert on NP ballots and vote disqualified
Insufficient experts named to register projects
Countries fail to register named experts in Global Directory
Nonresponsive to requests for experts and registration in Global Directory
18
Highlights of the June 2014 Meeting Only SC6/WG3 met
5 countries represented
15 experts on both days
13 resolutions, including - New project proposal by Republic of Korea on
classification of transients and accidents for PWRs
- Possible new proposal on ‘Stationary Steam Turbines – General Technical Requirements’
- Proposal for new structure by the Russian Federation on ‘Construction in the nuclear industry’
19
The next SC 6 meeting is tentatively scheduled for 5-6 June 2015 in San Antonio, Texas, USA, at the Grand Hyatt San Antonio preceding the American Nuclear Society’s Annual Meeting.
