MACCS version 1.5.11.1: A maintenance release of the code

Chanin, D.I.; Foster, James C.; Rollstin, J.A.; Miller, Lawrence M.

doi:10.2172/10104245

Cited by 7 publications

(5 citation statements)

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“…User's manual (Lynx, 1994(Lynx, , 1996, vs. ), user's manual ), programmer's manual , maintenance release (Chanin et al, 1993); maintained by U.S.…”

Section: Statusmentioning

confidence: 99%

Site characterization progress report: Yucca Mountain, Nevada. Number 15, April 1--September 30, 1996

1997

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DISTRIBUTION OF THIS DOCUMENT I S URPklMtm Washington, DC 20585 A p r i l 2 3 , 1997 NOTE TO READERS:During this reporting period, we released our revised Program Plan which outlines a focused, integrated program that will achieve key Program and statutory objectives. The plan identifies three near-term objectives: (1) updating in 1997 the regulatory framework for repository site characterization, (2) supporting a 1998 viability assessment, and (3) if the site is suitable, submitting a Secretarial site recommendation to the President in 2001 and a license application to the Nuclear Regulatory Commission in 2002. In support of the first near-term objective, we drafted a Notice of Proposed Rulemaking to amend the repository siting process. This notice was subsequently published in the Federal Register on December 16, 1996, which began a 60-day public comment period. Subsequent notices extended the comment period to May 16, 1997.Tunneling was completed in the Exploratory Studies Facility main drift, and the tunnel boring machine continued tunneling up the south ramp. In December 1996, we encountered worse ground conditions than expected, but even with these poor ground conditions, the tunnel boring machine reached the south portal on April 25,1997. The completion of the main drift marks a shift in emphasis from constructing the Exploratory Studies Facility to conducting scientific experiments in the tunnel and alcoves.The initial construction phase of the Thermal Testing Facility was completed and the first phase of the in situ heater tests began on schedule in August 1996. This eighteen month test will measure thermal effects on the rock and the moisture within the rock.Most of our site investigations and design and performance assessment activities this period were directed toward providing information for the 1998 viability assessment, our second near-term objective. Several studies and modeling activities were completed that provided new information on the potential percolation flux in the repository horizon. The new information indicated the potential for preferential water pathways and for a percolation flux higher than previously indicated.During the next period, we will continue modeling, testing, and data collection activities to reduce the uncertainty in the range of percolation flux that can be expected i? the repository horizon. In the Note to Readers for the 14th Progress Report, we indicated that we expected to issue the revised Waste Containment and Isolation Strategy during the first half of 1997. We will re-evaluate issuance of the strategy as a consequence of any changes to the predicted range c,f percolation flux rates. In addition, we will reassess the results from our on-going repository design and performance activities discussed in this progress report in light of the these same changes. 4-15Design Activity 1.1 1.3. PROGRESS REPORT #15 EXECUTIVE SUMMARYDuring the second half of fiscal year 1996, activities at the Yucca Mountain Site Characterization Proj...

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“…User's manual (Lynx, 1994(Lynx, , 1996, vs. ), user's manual ), programmer's manual , maintenance release (Chanin et al, 1993); maintained by U.S.…”

Section: Statusmentioning

confidence: 99%

Site characterization progress report: Yucca Mountain, Nevada. Number 15, April 1--September 30, 1996

1997

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“…Code System (MACCS) version 1.5. l I. l [Chanin et al, 1992] was utilized for the analysis of four hypothetical population distributions.…”

Section: Approachmentioning

confidence: 99%

Evaluation of population density and distribution criteria in nuclear power plant siting

Young¹

1994

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The NRC has proposed revisions to 10 CFR 100 which include the codification of nuclear reactor site population density limits to 500 people per square mile, at the siting stage, averaged over any radial distance out to 30 miles, and 1000 people per square mile within the 40-year lifetime of a nuclear plant. This study examined whether there are less restrictive alternative population density and/or distribution criteria which would provide equivalent or better protection to human health in the unlikely event of a nuclear accident. This study did not attempt to directly address the issue of actual population density limits because there are no U.S. risk standards established for the evaluation of population density limits. Calculations were performed using source terms for both a current generation light water reactor (LWR) and an advanced light water reactor (ALWR) design. The results of this study suggest that measures which address the distribution of the population density, including emergency response conditions, could result in lower average individual risks to the public than the proposed guidelines that require controlling average population density. Studies also indicate that an exclusion zone size, determined by emergency response conditions and reactor design (power level and safety features), would better serve to protect public health than a rigid standard applied to all sites.

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“…As a result of the code's development status, there are no plans to submit it to the government code centers. The software described in this report is intended for use by individuals familiar with the current version of MACCS and its documentation [Ch92]. It is requested of all recipients of this software that it not be disseminated to others without the authorization of LANL, the sponsor of this effort.…”

Section: Rationale For Code Modificationmentioning

confidence: 99%

“…For evacuation delay times of up to 10000 seconds, the accuracy of the timing was within 1 second. modifications should be adequately described in documentation for the new version of MACCS [Ch92].…”

Section: C7 Proper Interaction Between Plume Arrival Time and Exposurementioning

confidence: 99%

“…Under DOE sponsorship, as directed by the Los Alamos National Laboratory (LANL), the MACCS code (version 1.5.11.1) [Ch92] was modified to implement a series of improvements in its modeling of emergency response actions. The purpose of this effort has been to aid the Westinghouse Savannah River Company (WSRC) in its performance of the Level M analysis for the Savannah River Site (SRS) probabilistic risk analysis (PRA) of K Reactor [Wo90].…”

MACCS version 1.5.11.1: A maintenance release of the code

Cited by 7 publications

References 0 publications

Site characterization progress report: Yucca Mountain, Nevada. Number 15, April 1--September 30, 1996

Site characterization progress report: Yucca Mountain, Nevada. Number 15, April 1--September 30, 1996

Evaluation of population density and distribution criteria in nuclear power plant siting

A new emergency response model for MACCS. Final report

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