Nuclear reactor light water-cooled reactors

Regulatory Guide 1.133, Rev. 1, "Loose-Part Detection Program for the Primary System of Light-Water-Cooled Reactors", U.S. Nuclear Regulatory Commission, May 1981. 

When a nitrogen atom freshly produced by a nuclear reaction is broken away from an H2O molecule, the thermalized nitrogen atom may react with various radicals, ions and molecules in the immediately surrounding area of the aqueous phase. In a high radiation field, such as exists in the core of a light-water cooled reactor, the principal reaction partners will be the products of water radiolysis. In earlier laboratory studies (Schleiffer and Adloff, 1964) the following chemical forms and distribution of N produced in pure water were identified ... 

The use of micro fuel elements is being considered for WER-1000 reactors [X-2] and for a direct-flow light water cooled reactor with superheated steam at core outlet, a concept developed by the Pacific Northwest National Laboratory (PNNL, USA). However, both these reactors are not SMRs. The Fixed Bed Nuclear Reactor (FBNR) described in this report incorporates certain design approaches that could be of relevance to the VKR-MT. 

United States Atomic Energy Commission, The Safety of Nuclear Power Reactors Light Water Cooled) and Related Facilities, USAEC Report WASH-1250, USAEC, Washington, D.C. 

The Reactor Safety Study was prompted in part by a request from Senator John Pastore for a comprehensive assessment of reactor safety. The AEC s first response to this request was the WASH-1250 report entitled The Reactor Safety Study of Nuclear Power Reactors (Light Water-Cooled) and Related Facilities, which was published in final form in July 1973. However, WASH-1250 did not provide a probabilistic assessment of risk as requested in Senator Pastore s letter. At the time, relevant probabilistic estimates were quite limited in scope and/or highly subjective. For example, in a policy paper dated November 15, 1971, to the commissioners proposing an approach to the preparation of environmental reports, the regulatory staff estimated that the probability of accidents leading to substantial core meltdown was 10 per reactor-year. In retrospect, this was a highly optimistic estimate, but it typifies the degree to which meltdown accidents were considered "not credible."... 

LWRs were developed 50 years ago. Their successful implementation was based in part on experiences with subcritical fossil-fuel fired power technologies at that time. The number of supercritical FPPs worldwide is larger than that of nuclear power plants. Considering the evolutionary history of boilers and the abundant experiences with supercritical FPP technologies, the supercritical pressure light water cooled reactor is the natural evolution of LWRs. 

Y. Oka, S. Koshizuka, T. Jevremovic, Y. Ohno and K. Kitoh, Direct-Cycle Supercritical-Pressure, Light-Water-Cooled Reactors for Improving Economy and Plutonium Utilization, Proc. Global95, International Conference on Evaluation of Emerging Nuclear Fuel Cycle Systems, Versailles, France, September 11-14, 1995, 930-937 (1995)... 

T. Nakatsuka, Y. Oka and S. Koshizuka, Startup Thermal Considerations for Supercritical-Pressure Light Water-Cooled Reactors, Nuclear Technology, Vol. 134(3), 221-230 (2001) T. Nakatsuka, Y. Oka and S. Koshizuka, Start-up of Supersritical-pressure Light Wtater Cooled Reactors, Proc. ICONE-8, Baltimore, MD., April 2-6, 2000, ICONE-8304 (2000) T. T. Yi, Y. Ishiwatari, S. Koshizuka and Y. Oka, Startup Thermal Analysis of a High-Temperature Supercritical-Pressure Light Water Reactor, Journal of Nuclear Science and Technology, Vol. 41(8), 790-801 (2004)... 

J.H. Lee, S. Koshizuka and Y. Oka, Development of a LOCA Analysis Code for the Supercritical-Pressure Light Water Cooled Reactors, Annals of Nuclear Energy, Vol. 25 (16), 1341-1361 (1998)... 

Y. Oka and S. Koshizuka, Supercritical-pressure, once-through cycle light water cooled reactor concept, /ourna/ of Nuclear Science andTechnology, Vol. 38(12), 1081-1089 (2001)... 

F3. Fowler, T. W., R. L. Clark, J. M. Gruhlbe, and J. L. Russel Public Health Considerations of Carbon-14 Discharges from the Light-Water-Cooled Nuclear Power Reactor Industry, Report ORP/TAD-76-3, July 1976. 

FIG. 19.2. Main components of a pressurized light water cooled and -moderated nuclear power reactor (PWR) and a view of the Ringhals plant (Sweden) with 3 PWRs and 1 BWR. 

This order applies to all varieties of reactors including, but not limited to light water moderated reactors, heavy water moderated reactors, liquid metal cooled reactors, gas cooled reactors and short-pulse transient reactors. Space reactor power and propulsion systems and critical facilities require special design criteria. Attachment 4 is reserved for Nuclear Safety Design for critical facilities and space reactors. 

AR386 1.110 Cost-benefit analysis for radwaste systems for light-water-cooled nuclear power reactors... 

Water cooled reactors. 2. Boiling water reactors. 3. Nuclear reactor accidents. 4. Nuclear power plants — Accidents. 5. Nuclear reactors — Safety measures. 6. Light water graphite reactors. I. International Atomic Energy Agency. II. Series. 

ASTM E 185-82 (1982), Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels, E 706 (IF) , American Society for Testing and Materials. 

In 1986, an accident occurred at the Chernobyl Unit 4 reactor near Kiev in Ukraine. The Chernobyl reactor was a light water-cooled graphite-moderated (LWG) reactor. This accident led to the release of a large amoimt of airborne radioactivity and the death of many of the responders. As a result of this accident, several countries with smaller nuclear power programs ceased the pursuit of nuclear power electricity generation. 

Kotthoff, K. Graphite-moderated, light-water-cooled, pressure-tube reactors, in Ullmann s Encyclopedia of Industrial Chemistry, Volume A17 Nuclear Technology, p. 682-694 (1991)... 

Appendix I, Numerical Guides for Design Objectives and Limiting Conditions for Operation to Meet the Criterion As Low as Reasonably Achievable for Radioactive Material in Light-Water-Cooled Nuclear Power Reactor Effluents. 

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