Emergency Preparedness technology support to the Health and Safety Executive (HSE), Nuclear Installations Inspectorate (NII) of the United Kingdom. Appendix A

Technical Report · Tue Mar 01 00:00:00 EST 1994

DOI:https://doi.org/10.2172/10160726· OSTI ID:10160726

O`Kula, K R

The Nuclear Installations Inspectorate (NII) of the United Kingdom (UK) suggested the use of an accident progression logic model method developed by Westinghouse Savannah River Company (WSRC) and Science Applications International Corporation (SAIC) for K Reactor to predict the magnitude and timing of radioactivity releases (the source term) based on an advanced logic model methodology. Predicted releases are output from the personal computer-based model in a level-of-confidence format. Additional technical discussions eventually led to a request from the NII to develop a proposal for assembling a similar technology to predict source terms for the UK`s advanced gas-cooled reactor (AGR) type. To respond to this request, WSRC is submitting a proposal to provide contractual assistance as specified in the Scope of Work. The work will produce, document, and transfer technology associated with a Decision-Oriented Source Term Estimator for Emergency Preparedness (DOSE-EP) for the NII to apply to AGRs in the United Kingdom. This document, Appendix A is a part of this proposal.

• Research Organization: Savannah River Site (SRS), Aiken, SC (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: AC09-89SR18035
• OSTI ID: 10160726
• Report Number(s): WSRC-RP-93-1521; ON: DE94013861
• Resource Relation: Other Information: PBD: Mar 1994
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
GAS COOLED REACTORS
REACTOR SAFETY
REACTOR ACCIDENTS
SOURCE TERMS
UNITED KINGDOM
PROPOSALS
EMERGENCY PLANS
DECISION MAKING
FISSION PRODUCT RELEASE
TASK SCHEDULING
PLANNING
CONTRACTORS
220900
220502
210300
RADIOACTIVE EFFLUENTS
POWER REACTORS
NONBREEDING
GRAPHITE MODERATED