Health and Safety
Executive / Commission
Research:
Nuclear Safety
| Technical Area | Contract No | Report Ref | Title | Contractor |
|---|---|---|---|---|
| 2004 | CI/KT/36 | 03/8008/10.42 | Report on a Trial Dismantling and costing of an improved cable recovery strategy with seal replacement. | Canberra Harwell Ltd., |
| CI/KT/36 | 03/8008/10.72 | On load testing of Neutron Flux Detectors - A Review of accumulated data to February 2004. | Canberra Harwell Ltd., | |
| CI/KT/36 | 03/8008_10.11 | Report to define the MI Cable manufacturing route at Thermocoax. | Canberra Harwell Ltd | |
| CI/KT/36 | 03/8008/10.32 | Report on CET termination and post manufacture quality issues. | Canberra Harwell Ltd | |
| CI/KT/36 | 03/8008/10.91 | A Review of Status of Specifications for ex-core decector types. | Canerra Harwell Ltd | |
| CI/KT/36 | 03/8008/10.61 | On Load Testing of Neutron Flux Detectors - A review of Performance Limits. | Canberra Harwell Ltd. | |
| CI/KT/36 | 03 8008 10.21 | Report Defining Minimum IR requirements for MI Cables. | Canberra Harwell Ltd. | |
| CI/GNSR/34 | wp2 ade047 v10 | CEMSIS: Cost Effective Modernisation of Systems Important to Safety – WP2 contribution to final report: long V1.0. | BEG(UK) Ltd | |
| CI/GNSR/34 | wp5 ade049 | CEMSIS: Public Domain Case Study (for main report) – Appendix A.5 to Final Report. | BEG(UK) Ltd | |
| CI/GNSR/34 | wp1_avn021_v02 | CEMSIS: Appendix A.1 to Final Report – A Dependability Justification Framework for NPP Digital Instrumentation and Control Systems. | BEG(UK) Ltd | |
| CI/GNSR/34 | wp2_ade047_v10 | CEMSIS: Appendix A.2 to Final Report - Best Practice Guide on the Development of Safety Requirements for SIS Refurbishment. | BEG(UK) Ltd | |
| CI/GNSR/34 | wp3_final_report | CEMSIS: Appendix A.3 to Final Report –Justification of COTS-based systems. | BEG(UK) Ltd | |
| CI/GNSR/34 | Wp5_beg038 v 2.1 | CEMSIS: Appendix A.4 to Final Report – Final Report on CaseStudies. | BEG(UK) Ltd | |
| CI/GNSR/34 | wp5_ade049 | CEMSIS: Appendix A.5 to Final Report Extended Version – Public Domain Case Study | BEG(UK) Ltd | |
| CI/GNSR/34 | wp0_beg042_v2_0 | CEMSIS: Work Package 0 Final Extended Synthesis Report (first issue) | BEG(UK) Ltd | |
| CI/GNSR/34 | wp1_avn010 v6.1 | CEMSIS: Work Package 1 – A Dependability Justification Framework for NPP Digital Instrumentation and Control Systems. | BEG(UK) Ltd | |
| CI/GNSR/34 | wp3_edf037 v 03 | CEMSIS: Assessment and analysis guidelines for Off-The-Shelf Product-based Systems Important to Safety V03. | BEG(UK) Ltd | |
| CI/GNSR/34 | wp4_syc018v20_D4 | CEMSIS: Work Package 4/Deliverable D4 – Review and evaluation of sought-after properties of tools based on graphical languages of models and representations V20. | BEG(UK) Ltd | |
| CI/GNSR/34 | wp6_beg018_v1_1 | CEMSIS: D6.3.1 – Technological Implementation Plan v1.1. | BEG(UK) Ltd | |
| CI/GNSR/34 | wp1_avn021_v01 | CEMSIS: Work Package 1 Final Report Synthesis and Extended Version – A Dependability Justification Framework for NPP Digital Instrumentation and Control Systems. | BEG(UK) Ltd | |
| CI/GNSR/34 | wp0_beg041_v1 | CEMSIS: Work Package 0 Final Public Synthesis Report (Second Draft). | BEG(UK) Ltd | |
| 2003 | CI/KT/33.2 | 02/8004 10.05 | On Load testing of Neutron Flux detectors - A review of accumulated data (2001-2003). | Canberra Harwell Ltd |
| CI/KT/31.2 | 02/8004 10.81 | Technical Archiving Quality Check [PDF 169kb] | Canberra Harwell Ltd | |
| CI/KT/31.2 | 02/8004 10.22 | BF3 irradiation Lifetime at Sizewell B. | Canberra Harwell Ltd. | |
| CI/KT/31.2 | 02/8004 10.62 | Summary of recent MI Cable development issues. | Canberra Harwell Ltd | |
| CI/KT/36 | 03 8008 10.71 | On Load Testing of Neutron Flux Detectors - A Review of accumulated data to September 2003. | Canberra Harwell Ltd. | |
| CI/KT/36 | 03/8008 10.31 | Report on selection criteria for stores DC12As. | Canberra Harwell Ltd | |
| CI/KT/36 | 03 8008/10.41 | Improved Cable Recovery Strategy | Canberra Harwell Ltd | |
| CI/KT/35 | TR 3259 | Draft: Investigation and Recommendation on the use of Circuit simulation packages in the formal design of analogue based safety trip Equipment. | Alstec Ltd | |
| CI/KT/35 | TR3230/2 | The Use Of Circuit Modelling Tools for Analysis of Safety Trip Units. | Alstec Ltd | |
| CI/KT/36 | 03/8008 | A report produced for deliverable D1.4 under the 2003-2004 IMC Nucleonics Key Team programme. September 2003. | Canberra Harwell Ltd. | |
| 2002 | CI/KT/33.2 | 02/8004 | Review of DC12A Metal Ceramic Seal Development work. December 2002. | Canberra Harwell Ltd., |
| CI/KT/33.2 | 0180151042 | Review of Issues concering the Lifetime of BF3 Detectors Dec 2002. | Canberra Harwell Ltd | |
| 2001 | CI/KT/33.2 | WSSD01/8015/10.1 | Pulse Plateau Measurements on Installed Sizewell B Detectors. | Harwell Instruments Ltd |
| CI/KT/33.2 | WSSD01/8015/10.2 | On Load Testing of Neutron Flux Detectors - A Review of Accumulated Data. | Harwell Instruments Ltd | |
| CI/KT/33.2 | WSSD01/8015/10.3 | Metal Ceramic Seal Extended Temperature Trial. | Harwell Instruments Ltd. | |
| 2000 | ||||
| 1999 | CI/GNSR/33 | WSSD 1089/10.2 | Investigations of MI cable concentricity problems | Harwell Instruments |
| CI/GNSR/33 | WSSD 10889/10.3 | Evaluation of alternative metal ceramic seal designs | Harwell instruments | |
| CI/GNSR/33 | WSSD 10889/10.4 | Review of status of stored P8A detectors | Harwell instruments | |
| 1998 | ||||
| 1997 | CI/GNSR/21 | Determination of Methods of Software Reliability Quantification | RMC | |
| CI/GNSR/33 | Nucleonic Key Team | AEAT | ||
| 1996 | CI/GNSR/18 | LAW/09_1 | LAW - Feasibility Study | |
| CI/GNSR/18 | LAW/D1.1-3 | Assessment of User Requirements | ||
| CI/GNSR/18 | LAW/D1.1-2 | Assessment of User Requirements | ||
| 1995 | CI/GNSR/11 | AEA/CS/1766401533 | Survey of approaches to dependent failure issues in the UK | |
| CI/GNSR/21 | R94-1(N) J2313 | An Investigation into PLC Software Reliability. | RM CONSULTANTS | |
| CI/GNSR/22 | Computer Based Safety Systems Experience of one Application in Justifying in Another | RM CONSULTANTS | ||
| CI/GNSR/23 | Identification of Sources of Errors in Real Time Industrial Applications | RM CONSULTANTS | ||
| CI/GNSR/24 | C9125/PR/003 | System Design for Safety Assessment Report R3 Recommendations on Computer-Based Systems for Nuclear Power Stations. | NNC LTD | |
| CI/GNSR/27 | UK/NS/SK | The Design and Developments of Safety Kernels | U/YORK | |
| CI/GNSR/28 | NS/92/01 - C2002 | KERSD Project Identification of Key Elements Relating to Software Dependability | U/YORK | |
| 1994 | CI/GNSR/12 | AEA-RS-1337 | Description of a Software Benchmark derived from the DARTS project | |
| CI/GNSR/12 | AEA-RS-1325 | Description of the DARTS assessment data | ||
| CI/GNSR/15 | 45-03-R-01 | The Formal Verification of PLC Embedded Software | ||
| CI/GNSR/19 | 48/79149/D2.1b | Measurements to Support Software Dependability | ||
| CI/GNSR/19 | 48/79149/D2.1a | Review of Software Quality Modules | ||
| CI/GNSR/19 | 48/79149/D1.2 | Attributes to Indicate the Cost Effectiveness of Activities in Contributing to Software Dependability | ||
| CI/GNSR/20 | 4307/000/R/94/ 3013 | Reliability Quantification of Software -Based Systems by Dynamic Testing | ||
| CI/GNSR/24 | C9125/PR/003 | Recommendations on Computer- Based Systems for Nuclear Power Stations | ||
| CI/GNSR/24 | 9125/PWR/94/ REP/OO1 | System Design for Safety Assessment - Report R1 Design Bases and Structures for Computer Based Systems on Nuclear Power Plants | ||
| CI/GNSR/25 | 244.20750 | Systems Design Amenable to Safety Demonstration | ||
| CI/GNSR/27 | UK/NS/SK | The Design and Developments of Safety Kernels | U/YORK | |
| CI/GNSR/28 | NS/92/01/D3 | Obtaining and Assessing Dependable Software, Volume 3 Appendix B: The Dependability References Database | ||
| CI/GNSR/28 | NS/92/01/D4 | Obtaining and assessing Dependable Software, Final Report - Deliverable D4 | ||
| CI/GNSR/28 | NS/92/01/D3/v1 | Obtaining and assessing Dependable Software, Volume 1: Evaluative Report | ||
| 1993 | CI/GNSR/08 | AEA/RS/1302 | Guidelines for the Development of Multi-processing Safety Critical Systems | AEA Reactor Services |
| - | AEA-RS-1323 [LITTLE93] | Directions in Safety Critical Systems: The Need for Evidence from Disparate Sources to Evaluate Software Safety | ||
| CI/AGR/18 | AEA-RS1321 | The Archiving and Design of Operational Data Pertinent to the Safe Operation of Reactor Control and Protection Instrumentation | ||
| CI/AGR/30 | AEA-RS-1259 | Interim Report on the Investigations into EMC in Digital Systems | ||
| CI/AGR/32 | AEA-RS-1331 | Final Report on the Development of Radiation Tolerant BF3 Counters | ||
| CI/AGR/32 | AEA-RS1322 | Reactor Safety Instrument Response to 50Hz Differential Earth Voltages | ||
| CI/GNSR/08 | AEA-RS-1197 | Analysis of a Multiprocessing System Fragment Using CCS | ||
| CI/GNSR/08 | AEA-RS-1302 | Guidelines for the Development of Multi - Processing Safety Critical Systems | ||
| CI/GNSR/08 | AEA-RS-1224 | Review of a System Specification after CCS Modelling | ||
| CI/GNSR/11 | C8662/ESD/ AEA-93/REP/01 | Data for software systems important to safety | ||
| CI/GNSR/12 | AEA-RS-1340 | Guidance on the Cost Effectiveness of Different Routes Arising from the DARTS Project | ||
| CI/GNSR/12 | AEA-RS-1336 | Report on the Licensing of the DARTS Channels | ||
| CI/GNSR/12 | AEA-RS-1329 | Report on the Second Phase of Operational Testing of the DARTS Demonstrator | ||
| CI/GNSR/12 | AEA-RS-1330 | Report on the third phase of operational testing of the DARTS demonstrator | ||
| CI/GNSR/12 | AEA-RS1326 | Methods, Tools & Production Effort in the DARTS Experiment | ||
| CI/GNSR/12 | AEA-RS1325 | Description of the DARTS Assessment Data | ||
| CI/GNSR/12 | AEA-RS-1228 | Report on the first phase of operational testing of the DARTS demonstrator system | ||
| CI/GNSR/13 | AEA-RS1323 | Managing the Reuse of Safety Critical Software | ||
| CI/GNSR/13 | AEA-RS-1315 | Reverse Engineering for Safety Critical Software | ||
| CI/GNSR/14 | RRA/12248 | Optimising Software Test Coverage | ||
| CI/GNSR/19 | 48/79149, D1.1 | A Taxonomy of Software Dependability Related Activities | ||
| CI/GNSR/20 | 4307/000/R/ 94/3004 | Reference 9.1.1 : Reliability Quantification of Software-Based Systems by Dynamic Testing | ||
| CI/GNSR/26 | BD 6133 | An Evaluation of Object Oriented Technology in Safety Critical Systems | ||
| CI/GNSR/26 | BD 6097 | Evaluation of Development Methods | ||
| CI/GNSR/26 | BD 6046 | Use Of Object Oriented Technology in Safety Critical Systems | ||
| CI/GNSR/27 | CI/GNSR/27/ WP1 | Specifying and Implementing Safety Services, Work Package 1: The Design and Development of Safety Kernels | ||
| CI/GNSR/27 | CI/GNSR/27/ SK | Safe Nucleus Detailed Design, Work Package 1: The Design and Development of Safety Kernels. | ||
| CI/GNSR/27 | - | Preliminary Design Report | ||
| CI/GNSR/27 | NS/92/01/D1 | Identification of Key Elements Relating to Software Dependability - Refinement of Objectives | ||
| PC/GNSR/16 | AEA-RS-4330 | In Plant Monitoring of Aging in Polymeric Materials | ||
| 1992 | C569 (8319) | RRA/11549 | Software Lifecycle Assessment Technique (SLAT) | |
| C570 (8142) | RRA/11517 | Fault Resistant Software Systems | ||
| C571 (8143) | RRA/11590 | Formal Methods for Safety Principles | ||
| C572 (8144) | RRA/11516 | Safe Programming of Programmable Logic Controllers | ||
| CI/AGR/02 | AEA-RS-1152 | The Archiving of Design and Operational Data Pertinent to the Safe Operation of Reactor Control and Protection Instrumentation | ||
| CI/AGR/02 | AEA-RS-6 | Information and Data Archiving | ||
| CI/GNSR/08 | AEA-RS-1161 | Description of a Multi-Processing System Fragment for uses in Safety - Critical Applications | ||
| CI/GNSR/08 | AEA-RS-6061 | Formal Methods in Safety Critical Systems | ||
| CI/GNSR/13 | AEA-RS-1207 | Software Reuse as a Means of Enhancing Reliability |