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Title: IRIS: Proceeding Towards the Preliminary Design

Abstract

The IRIS (International Reactor Innovative and Secure) project has completed the conceptual design phase and is moving towards completion of the preliminary design, scheduled for the end of 2002. Several other papers presented in this conference provide details on major aspects of the IRIS design. The three most innovative features which uniquely characterize IRIS are, in descending order of impact: 1. Safety-by-design, which takes maximum advantage of the integral configuration to eliminate from consideration some accidents, greatly lessen the consequence of other accident scenarios and decrease their probability of occurring; 2. Optimized maintenance, where the interval between maintenance shutdowns is extended to 48 months; and 3. Long core life, of at least four years without shuffling or partial refueling. Regarding feature 1, design and analyses will be supplemented by an extensive testing campaign to verify and demonstrate the performance of the integral components, individually as well as interactive systems. Test planning is being initiated. Test results will be factored into PRA analyses under an overall risk informed regulation approach, which is planned to be used in the IRIS licensing. Pre-application activities with NRC are also scheduled to start in mid 2002. Regarding feature 2, effort is being focused on advancedmore » online diagnostics for the integral components, first of all the steam generators, which are the most critical component; several techniques are being investigated. Finally, a four year long life core design is well underway and some of the IRIS team members are examining higher enrichment, eight to ten year life cores which could be considered for reloads. (authors)« less

Authors:
 [1];  [2];  [3];  [4];  [5];  [6];  [7];  [8];  [9];  [10];  [11];  [12];  [13];  [14];  [15];  [16]
  1. Westinghouse Electric Company (United States)
  2. BNFL UK (United Kingdom)
  3. Politecnico di Milano, Piazza Leonardo da Vinci, 32, 20133 Milano (Italy)
  4. Massachusetts Institute of Technology, 77 massachusetts avenue, cambridge, ma 02139-4307 (United States)
  5. Univ. California Berkeley, Berkeley CA 94720 (United States)
  6. Tokyo Institute of Technology, 2-12-1 O-okayama, Meguro-ku, Tokyo 152-8550 (Japan)
  7. Bechtel Power Corp (United States)
  8. Ansaldo Nuclear Division, C.so Perrone, 25, Genova 16161 (Italy)
  9. Equipos Nucleares SA - ENSA (Spain)
  10. Universita di Pisa, Dipartimento di Ingegneria Meccanica Nucleare e della Produzione, Via Diotisalvi 2, 56126 Pisa (Italy)
  11. Instituto Nacional de Investigaciones Nucleares, Km 36.5 Carretera Mexico-Toluca, Ocoyoacac 52045, Edo. de Mexico (Mexico)
  12. NUCLEP, Itaguai (Brazil)
  13. Tennessee Valley Authority - TVA (United States)
  14. CNEN, Comissao Nacional de Energia Nuclear, Rua General Severiano 90, Rio de Janeiro, RJ-22-294-900 (Brazil)
  15. Oak Ridge National Laboratory - ORNL, 1 Bethel Valley Rd, Oak Ridge, TN 37830 (United States)
  16. Faculty of Electrical Engineering and Computing, University of Zagreb, Unska 3, HR-10000 Zagreb (Croatia)
Publication Date:
Research Org.:
The ASME Foundation, Inc., Three Park Avenue, New York, NY 10016-5990 (United States)
OSTI Identifier:
21062368
Resource Type:
Conference
Resource Relation:
Conference: ICONE 10: 10. international conference on nuclear engineering, Arlington - Virginia (United States), 14-18 Apr 2002; Other Information: Country of input: France
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; ACCIDENTS; CONFIGURATION; DESIGN; ENRICHMENT; HAZARDS; INTEGRALS; LICENSING; MAINTENANCE; PERFORMANCE; PLANNING; PROBABILITY; REACTOR SAFETY; REACTOR SHUTDOWN; REGULATIONS; STEAM GENERATORS; TESTING

Citation Formats

Carelli, M, Miller, K, Lombardi, C, Todreas, N, Greenspan, E, Ninokata, H, Lopez, F, Cinotti, L, Collado, J, Oriolo, F, Alonso, G, Morales, M, Boroughs, R, Barroso, A, Ingersoll, D, and Cavlina, N. IRIS: Proceeding Towards the Preliminary Design. United States: N. p., 2002. Web.
Carelli, M, Miller, K, Lombardi, C, Todreas, N, Greenspan, E, Ninokata, H, Lopez, F, Cinotti, L, Collado, J, Oriolo, F, Alonso, G, Morales, M, Boroughs, R, Barroso, A, Ingersoll, D, & Cavlina, N. IRIS: Proceeding Towards the Preliminary Design. United States.
Carelli, M, Miller, K, Lombardi, C, Todreas, N, Greenspan, E, Ninokata, H, Lopez, F, Cinotti, L, Collado, J, Oriolo, F, Alonso, G, Morales, M, Boroughs, R, Barroso, A, Ingersoll, D, and Cavlina, N. Mon . "IRIS: Proceeding Towards the Preliminary Design". United States.
@article{osti_21062368,
title = {IRIS: Proceeding Towards the Preliminary Design},
author = {Carelli, M and Miller, K and Lombardi, C and Todreas, N and Greenspan, E and Ninokata, H and Lopez, F and Cinotti, L and Collado, J and Oriolo, F and Alonso, G and Morales, M and Boroughs, R and Barroso, A and Ingersoll, D and Cavlina, N},
abstractNote = {The IRIS (International Reactor Innovative and Secure) project has completed the conceptual design phase and is moving towards completion of the preliminary design, scheduled for the end of 2002. Several other papers presented in this conference provide details on major aspects of the IRIS design. The three most innovative features which uniquely characterize IRIS are, in descending order of impact: 1. Safety-by-design, which takes maximum advantage of the integral configuration to eliminate from consideration some accidents, greatly lessen the consequence of other accident scenarios and decrease their probability of occurring; 2. Optimized maintenance, where the interval between maintenance shutdowns is extended to 48 months; and 3. Long core life, of at least four years without shuffling or partial refueling. Regarding feature 1, design and analyses will be supplemented by an extensive testing campaign to verify and demonstrate the performance of the integral components, individually as well as interactive systems. Test planning is being initiated. Test results will be factored into PRA analyses under an overall risk informed regulation approach, which is planned to be used in the IRIS licensing. Pre-application activities with NRC are also scheduled to start in mid 2002. Regarding feature 2, effort is being focused on advanced online diagnostics for the integral components, first of all the steam generators, which are the most critical component; several techniques are being investigated. Finally, a four year long life core design is well underway and some of the IRIS team members are examining higher enrichment, eight to ten year life cores which could be considered for reloads. (authors)},
doi = {},
url = {https://www.osti.gov/biblio/21062368}, journal = {},
number = ,
volume = ,
place = {United States},
year = {2002},
month = {7}
}

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